ML23128A109
| ML23128A109 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/08/2023 |
| From: | Borgen T Northern States Power Co |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-Pl-23-011 | |
| Download: ML23128A109 (1) | |
Text
1717 Wakonade Drive fl, Xcel Energy Welch, MN 55089
May 08, 2023 L-Pl-23-011 Tech Spec 5.6.1 ISFSI Tech Spec 5.2
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Prairie Island Nuclear Generating Plant, Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed Facility Operating License Nos. DPR-42 and DPR-60
Prairie Island Independent Spent Fuel Storage Installation Docket No. 72-10 Renewed Materials License No. SNM-2506
2022 Annual Radiological Environmental Monitoring Program Report
Pursuant to the requirements of Prairie Island Nuclear Generating Plant Technical Specifications, Section 5.6.1 and ISFSI Technical Specifications, Section 5.2, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submits the enclosed Annual Radiological Environmental Program Report for the period of January 1, 2022 through December 31, 2022.
Summary of Commitments
This letter makes no new commitments and no revisions to existing commitments.
£//y-Timothy P. Borgen Plant Manager, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota
Enclosure Document Control Desk L-PI-23-011 Page 2
cc: Administrator, Region III, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC Director of NMSS, USNRC Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator ENCLOSURE
ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION
Radiological Environmental Monitoring Program
JANUARY 1, 2022 - DECEMBER 31, 2022
74 pages to follow
~*L ATI Environmental, Inc.
Jr l( /"'\\I Midwest Laboratory 700 Landwe hr Ro >d
- No rthbr ook, IL 60062-23 10 ph o ne (847) 5 64-0700
- fa x (847) 564 - 5 17
XCEL ENERGY CORPORATION
PRAIRIE ISLAND NUCLEAR GENERATING PLANT
ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION
Radiological Environmental Monitoring Program
January 1 to December 31, 2022
Docket No. 50-282 Renewed Operating License No. DPR-42 Docket No. 50-306 Renewed Operating License No. DPR-60
ISFSI Docket No. 72-10 Renewed License No. SNM-2506
Prepared under Contract by
ATI ENVIRONMENTAL, Inc.
MIDWEST LABORATORY
Project No. 8010
Approved :
Ashok Banavali, Ph.D.
Laboratory Manager PREFACE
The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, operated by Northern States Power Co. - Minnesota, for XCEL Energy Corporation.
The report was prepared by Environmental, Inc., Midwest Laboratory.
ii TABLE OF CONTENTS
Section Page
Preface.................................................................................................................................................... ii
List of Tables.......................................................................................................................................... iv
List of Figures.......................................................................................................................................... v
1.0 INTRODUCTION
..................................................................................................................................... 1
2.0
SUMMARY
.............................................................................................................................................. 2
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)............................................ 3
3.1 Program Design and Data Interpretation....................................................................................... 3 3.2 Program Description...................................................................................................................... 4 3.3 Program Execution........................................................................................................................ 5 3.4 Laboratory Procedures.................................................................................................................. 5 3.5 Program Modifications................................................................................................................... 5 3.6 Land Use Census.......................................................................................................................... 6
4.0 RESULTS AND DISCUSSION................................................................................................................ 7
4.1 Atmospheric Nuclear Detonations and Nuclear Acci dents............................................................ 7
4.2 Summary of Preoperational Data.................................................................................................. 7
4.3 Program Findings.......................................................................................................................... 8
5.0 FIGURES AND TABLES........................................................................................................................ 12
6.0 REFERENCES
CITED.......................................................................................................................... 24
APPENDICES
A Interlaboratory Comparison Program Results....................................................................................... A-1 Attachment A, Acceptance Criteria for "Spiked" Samples................................................................ A-2
B Data Reporting Conventions................................................................................................................. B-1
C Annual Average Effluent Concentration Limits of Radioactivity in Air and Water Above Background in Unrestricted Areas.......................................................................................... C-1
D Sampling Location Maps.....................................................................................................................D-1
E Special Well and Surface Water Samples...........................................................................................E-1
iii LIST OF TABLES
No. Title Page
5.1 Sample Collection and Analysis Program................................................................................................. 15
5.2 Sampling Locations................................................................................................................................... 16
5.3 Missed Collections and Analyses.............................................................................................................. 19
5.4 Radiological Environmental Monitoring Program Summary...................................................................... 20
In addition, the following tables can be found in the Appendices:
Appendix A
A-1 Environmental Resources Associates, Crosscheck Program Results.....................................................A-3
A-2 Program Results; (TLDs)..................................................................................................................... A-4
A-3 In-house "Spiked" Samples................................................................................................................. A-6
A-4 In-house Blank Samples...................................................................................................................... A-9
A-5 In-house "Duplicate" Samples........................................................................................................................ A-11
A-6 Department of Energy MAPEP comparison results.................................................................................A -15
A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement)............A-17
Appendix C
C-1 Average Annual Effluent Concentration Limits of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas................................................................................. C-2
Appendix E
E-4.1 Sample collection and analysis program................................................................................................ E-5
E-4.2 Sampling locations................................................................................................................................. E-6
E-4.3 REMP Summary..................................................................................................................................... E-8
E-4.4 REMP Complete Data Tables................................................................................................................ E-9
E-4.5 Supplementary Data Tables.................................................................................................................. E-14
iv LIST OF FIGURES
No. Title Page
5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control............................................................................................................................... 13
5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6,7) versus control location (P-1).................................................................................... 14
MAPS
Appendix D Title Page
TLD locations within a one mile radius..................................................................................................... D-2 TLD locations, Controls.............................................................................................................................. D-3 TLD locations, surrounding the ISFSI Area................................................................................................ D-3 TLD locations within a five mile radius..................................................................................................... D-4
REMP sampling points within a one mile radius...................................................................................... D-5 REMP sampling points within a five mile radius....................................................................................... D-6 REMP sampling points, Control locations............................................................................................... D-7
Appendix E
Groundwater Monitoring Well locations................................................................................................... E-15
v
1.0 INTRODUCTION
This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2022.
This program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.
Tabulations of the individual analyses made during the year are not included in this report.
These data are included in a reference document (Environmental, Inc., Midwest Laborator y, 2022b) available at Prairie Island Nuclear Generating Plant.
Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co.-
Minnesota. The plant has two 575 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974.
1 2.0
SUMMARY
The Radiological Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Offsite Dose Calculation Manual for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.
Results for 2022 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
3.1 Program Design and Data Interpretation
The purpose of the Radiological Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).
Sources of environmental radiation include the following:
(1) Natural background radiation arising from cosmic rays and primordial radionuclides;
(2) Fallout from atmospheric nuclear detonations;
(3) Releases from nuclear power plants;
(4) Industrial and medical radioactive waste; and
(5) Fallout from nuclear accidents.
In interpreting the data, effects due to the plant must be distinguished from those due to other sources.
A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.
An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plants monitoring program includes analyses for tritium and iodine-131. Most samples are analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10%
of the total activity of fission products 10 days af ter reactor shutdown. Alternatively, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered radiological impact indicators.
The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and - 60, and zinc-65, are activation products and arise from activation of corr osion products. They are typical components of a nuclear power plants effluents, but are not produced in significant quantities by nuclear detonations.
3 3.1 Program Design and Data Interpretation (continued)
Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the plant became operational. Results of the plants monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.
3.2 Program Description
The sampling and analysis schedule for the radiological environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generat ing Plant, 2022). Maps of fixed sampling locations are included in Appendix D.
To monitor the airborne environment, air is sampled by continuous pumping at six stations, four site boundary indicators (P-2, P-3, P-4 and P-7), located in the highest calculated D/Q sectors, one community indicator (P-6), and one control (P-1). The particulates are collected on membrane filters, airborne iodine is trapped by activated charcoal canisters. Particulate filters are analyzed for gross beta activity and charcoal canisters for iodine-131. Quarterly composites of particulate filters from each location are analyzed for gamma-emitting isotopes.
Offsite ambient gamma radiation is monitored at thirty -four locations, using CaSO 4:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly.
Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI)
Facility by twenty CaSO 4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage c asks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.
To monitor the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are collected quarterly from five locations near the plant and analyzed for tritium and gamma-emitting isotopes.
River water is collected weekly at two locations, one upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Drinking water is collected weekly from the City of Red Wing well. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
4 3.2 Program Description (continued)
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sedimen t is collected semi-annually from one location. All samples are analyzed for gamma -emitting isotopes.
3.3 Program Execution
The Program was executed as described in the preceding section in 2022 with the following exceptions:
(1) Airborne Particulates /Airborne Iodine
The air sampler at location P-2 was found with 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> less than expected on the timer for the week ending 4/20/22. Sample declared missing due to insufficient running time.
The charcoal canister used for sampling at location P-2 for the week ending 11/16/22 was inadvertently also used for sampling at location P-4 for the week ending 11/23/22. This sampling error did not result in a missed sample because the sample was analyzed and a
< LLD value was assigned for both weeks.
3.4 Laboratory Procedures
The iodine-131 analyses in drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method, solvent extraction and subsequent beta counting.
Gamma-spectroscopic analyses were performed us ing high-purity germanium (HPGe) detectors.
Levels of iodine-131 in cabbage and natural vegetation and concentrations of airborne iodine -131 in charcoal samples were determined by gamma spectroscopy.
Tritium concentrations were determined by liquid scintillation.
Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.
Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S.
Department of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for M easurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.
Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2018). The QA Program includes participation in Interlaboratory Comparison (cro sscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.
3.5 Program Modifications
None.
5 3.6 Land Use Census
In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest residence, nearest milk animals, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and September 30. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the radiological environmental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after September of the year in which the land use census was conducted.
This land use census ensures the updating of the radiological environmental monitoring program should sampling locations change within the 5-mile radius from the plant.
The Land Use Census was conducted during September 2022. The ranking of the highest D/Q garden remained the same for 2022 as 2021, Suter (SSE at 0.6 miles). The highest D/Q residence remained the same for 2022 as for 2021, Sellers (WNW at 0.7 miles).
The Minnesota and Wisconsin Departments of Natural Resources were both consulted and both confirmed that no irrigation permits had been issued the past year for crop fields within the file mile Mississippi River area downstream of the Prairie Island Plant. Plant biologists conducted visual surveys while electro-fishing and visual observations were taken while driving. No irrigating was observed. Therefore, no crop sampling was performed.
There are no dairy farms within a 5-mile radius of the plant therefore no milk samples were collected.
Vegetation samples were taken from three close gardens in the vicinity of the plant this year plus a control site.
There were no land use changes within five miles of the plant resulting in new special interes t areas such as: new population centers, new residences, new schools or recreation centers.
6 4.0 RESULTS AND DISCUSSION
All scheduled collections and analyses were made in 2022 except those listed in Table 5.3.
The results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents
There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2022. The Fukushima Daiichi nuclear accident occurred March 11, 2011.
There were no reported atmospheric nuclear tests in 2022. The last reported test was conducted on October 16, 1980 by the Peoples Republic of China.
4.2 Summary of Preoperational Data
The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in fallout declined yearly from a level of 12,167 pCi/m3 to 1,020 pCi/m3, and these declining values are reflected throughout the various media tested.
In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during pre -
operational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m 3.
Average present day levels have stabilized at around 0.025 pCi/m3. Airborne radioiodine remained below detection levels.
In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137, I-131, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs -137 and I-131 are below detection levels.
Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-137.
Gross beta measured in soil averaged 52 pCi/g.
The aqueous environment was monitored by testing of river, well and lake waters, bottom sediments, fish, aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium measure below a detection limit of approximately 160 pCi/L. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L for well water, and11.0 pCi/L for lake water. Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCi/g. Cs -137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g, respectively. Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g, 46.0 pCi/g, and 13.6 pCi/g, respectively.
7 4.3 Program Findings
Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
Ambient Radiation (TLDs)
Ambient radiation was measured in the general area of the site boundary, at the outer ring 4 - 5 mi.
distant from the Plant, at special interest areas and at one control location. The means ranged from 16.6 mR/91 days at inner ring locations to 16.8 mR/91 days at outer ring locations. The mean at special interest locations was 16.2 mR/91 days and 17.5 mR/91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were comparable to 2021 dose rates and consistent with results from previous y ears. The results are tabulated below. No plant effect on ambient gamma radiation measurements was indicated (Figure 5-1).
Average (Inner and Average (Inner and Year Outer Rings) Control Year Outer Rings) Control 2001 16.8 17.2 2012 16.5 16.5
2002 17.4 16.9 2013 15.1 16.0 2003 16.2 16.0 2014 15.3 16.2 2004 17.6 17.6 2015 16.0 17.4 2005 16.8 16.3 2016 16.7 17.4 2006 16.6 16.6 2017 16.1 16.3 2007 17.5 17.7 2018 16.6 17.4 2008 16.9 17.1 2019 15.8 15.3 2009 15.9 16.3 2020 15.4 14.2 2010 16.0 16.0 2021 16.4 15.9 2011 15.7 15.7 2022 16.7 17.5
Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates (mR/91 days).
ISFSI Facility Oper ations Monitoring Ambient radiation was measured inside the ISFS I earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates averaged 203.5 mR /91 days inside the ISFSI earth berm and 24.9 mR/91 days outside the ISFSI earth berm. Three additional casks we re placed on the ISFSI pad in 20 22, a total of fifty loaded casks remain. The higher levels insi de the earth berm are expected, due to the loaded spent fuel casks being in direct line-of-sight of the TLDs.
Ambient radiation levels measured outside the ea rth berm show a slight increase as compared to other offsite dose rates around the plant. The cu mulative average of the two special Prairie Island Indian Community TLDs (Locations P-07S and P-08S) measured 15.7 and 15.2 mR/91 days.
Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7A - 4, TN-40 Dose Rates at Short Distances. Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).
8 Airborne Particulates
Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1999 through 2006, and also in 2008 through 201 9. The elevated activity observed in 2007 was attributed to construction activity in the area, an increase in dust and consequent heavier particulate filter loading.
Average annual gross beta concentrations in airborne particulates were 0.0 30 pCi/m3 for indicator locations and 0.031 pCi/m3 for the control location and similar to levels observed from 1999 through 2006 and 2008 to 2021. The results are tabulated below.
Average of Year Indicators Control Concentration (pCi/ m3) 2001 0.023 0.023 2002 0.028 0.023 2003 0.027 0.025 2004 0.025 0.026 2005 0.027 0.025 2006 0.026 0.025 2007 0.037 0.031 2008 0.028 0.027 2009 0.029 0.029 2010 0.025 0.025 2011 0.026 0.027 2012 0.031 0.032 2013 0.027 0.028 2014 0.026 0.026 2015 0.029 0.029 2016 0.027 0.027 2017 0.026 0.025 2018 0.027 0.027 2019 0.023 0.023 2020 0.027 0.025 2021 0.030 0.029 2022 0.030 0.031 Average annual gross beta concentrations in airborne particulates.
Gamma spectroscopic analysis of quarterly composit es of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), was detected in all samples, with an average activity of 0.082 pCi/m3 for indicator locations and 0.084 pCi/m3 at the control location. All other isotopes were below the lower limit of detection.
There was no indication of a plant effect.
Airborne Iodine
Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/m3 in all samples. There was no indication of a plant effect.
9 Drinking Water
In drinking water from the City of Red Wing well, tritium activity me asured below a detection limit of 166 pCi/L for all samples.
Gross beta concentrations averaged 8.9 pCi/L throughout the year, ranging from 6.5-12.1 pCi/L.
These concentrations are consistent with the 2021 average of 9.2 pCi/L and with levels observed from 2000 through 2020. The most likely contribution is the relatively high levels of naturally -
occurring radium. Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 20 22 data of any effect of plant operation.
Year Gross Beta concentration (pCi/L)
2000 10.1 2001 8.3 2002 8.7 2003 9.9 2004 9.8 2005 11.5 2006 13.4 2007 11.6 2008 11.6 2009 11.4 2010 11.7 2011 12.4 2012 11.8 2013 12.2 2014 11.5 2015 11.4 2016 12.3 2017 10.1 2018 10.2 2019 9.7 2020 8.6 2021 9.2 2022 8.9 Average annual gross beta concentrations in drinking water.
River Water
Analyses for H-3 in river water was below an LLD of 166 pCi/L for all eight quarterly composites from both the upstream and downstream locations for 2022. Gamma-emitting isotopes were below detection limits in all samples. In summary, the data for 2022 show no radiological effects from the plant operation.
10 Well Water
Water samples tested from the control well, P-43 (Peterson Farm) and from four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm) showed no tritium detected above a detection limit of 1 72 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2022 show no radiological effects of the plant operation.
Broadleaf Vegetation and Crops
Four samples of broadleaf vegetation, cabbage leaves, were collected in August 2022 and analyzed for gamma-emitting isotopes, including iodine-131. The I-131 level was below 0.034 pCi/g wet weight in all samples. With exceptions for naturally-occurring beryllium-7 and potassium-40, all other gamma-emitting isotopes were below their respective detection limits.
There was no indication of a plant effect.
Field sampling personnel conducted an annual land use survey and found no river water taken for irrigation into fields within five miles downstream from the Prairie Island Plant. The collection and analysis of corn samples was not required since the fields have not been irrigated.
Fish
Fish were collected in June and September 2022 and analyzed for gamma-emitting isotopes.
Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.
Aquatic Insects or Periphyton
Aquatic insects (invertebrates) or periphyton were collected in June and September 2022 and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes measured below detection limits with the exception of naturally occurring potassium-40 which was detected in all four samples. There was no indication of any plant effect.
Bottom and Shoreline Sediments
Upstream and downstream bottom sediments and downstream recreational area shoreline sediments were sampled in June and September 2022. All gamma-emitting isotopes measured below detection limits with the exception of naturally occurring potassium-40 which was detected in all four bottom sediment samples and both shoreline sediment samples. There was no indication of any plant effect.
11 5.0 FIGURES AND TABLES
12 Figure 5.1 Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.
I -+- Indicators
20
19
18
17,,.. \\ I /\\ ) ~ / "-...._,______
16 " ~ V ~ V --.., / ~ v ~ /
V \\ V "'i'----V 15 l.----'
14
13
12
11
10
--+- Control
20
19
18 17.... / 1"- ' ) \\. / ~ -- /
__. (' "' ~V '\\ / \\ I 16 "'- / '\\ """---.... --., _,..... \\ I 15....
14 ~ I 13
12
11
10
13 Figure 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
Indicators (P-2,3,4,6,7) 0.039....., I 0.037 j../ I Elevated due to construction activity
0.035 '\\ --r-----._ I ~
0.033 I \\
0.031 I \\
0.029 I \\ J \\ )"------0
.....___ I t"""'"" I\\ I \\ / "' /
0.027 0.025 I I"-. / ~ \\ __...--1 ~v ~.......... \\ /
0.023 I \\ V
0.021 0.019 0.017 0.015
-+- Control (P-1)
0.039
0.037
0.035
0.033
0.031 J\\
0.029 J\\ I \\ /
0.027 I \\ / \\ I )"- I I
0.025 /.........._ I \\ V 'IV \\ I "'
0.023 V \\ V
0.021
0.019
0.017
0.015
14 Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant.
Collection Analysis Location Type and Type and Medium No. Codes (and Type) a Frequency b Frequency c
Ambient radiation (TLD's) 54 P-01A - P-10A C/Q Ambient gamma P-01B - P-15B P-01S - P-08S P-01IA - P-08IA P-01IB - P-08IB P-01IX-P-04IX, P-01C
Airborne Particulates 6 P-1(C), P-2, C/W GB, GS (QC of P-3, P-4, P-6, P-7 each location)
Airborne Iodine 6 P-1(C), P-2, P-3, P-4, P-6, P-7 C/W I-131
River wa ter 2 P-5(C), P-6 G/W GS(MC), H-3(QC)
Drinking water 1 P-11 G/W GB(MC), I-131(MC)
Well water 5 P-6, P-8, P-9, P-24, G/Q H-3, GS P-43 (C)
Edible cultivated crops 1 P-30(C) G/A GS (I-131)
L eafy green vegetables 4 P-8, P-24, P-28, P-38(C) G/A GS (I-131)
Fish (three species, edible portion ) 2 P-19(C), P-13 G/SA GS
Periphyton or invertebrates 2 P-40(C), P-6 G/SA GS
Bottom sedimen t 2 P-20(C), P-6 G/SA GS
Shoreline sediment 1 P-12 G/SA GS
a Location codes are defined in Table 5.2. Control stations are indicated by (C). All other stations are indicators.
b Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows:
W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.
c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, I-131 = iodine-131.
Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
15 Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.
Distance and Direction Code Typea Collection Site Sample Typeb from Reactor
P-1 C Air Station P-1 AP, AI 11.8 mi @ 316o/NNW
P-2 Air Station P-2 AP, AI 0.5 mi @ 294o/WNW P-3 Air Station P-3 AP, AI 0.8 mi @ 313o/NW P-4 Air Station P-4 AP, AI 0.4 mi @ 359o/N
P-5 C Upstream of Plant RW 1.8 mi @ 11o/N P-6 Lock and Dam #3 & Air Station P-6 AP, AI, RW 1.6 mi @ 129 o /SE WW, BS, BO c
P -7 Air Station P-7 AP, AI 0.5 mi @ 271 o /W P -8 Community Center WW 1.0 mi @ 321 o /WNW P -9 Plant Well #2 WW 0.3 mi @ 306 o /NW P -11 Red Wing Service Center DW 3.3 mi @ 158 o /SSE P-12 Downstream of Plant SS 3.0 mi @ 116 o /ESE P-13 Downstream of Plant F c 3.5 mi @ 113 o /ESE
P -19 C Upstream of Plant F c 1.3 mi @ 0 o /N
P-20 C Upstream of Plant BS 0.9 mi @ 45 o /NE P-24 Suter Residence WW 0.6 mi @ 158 o /SSE P-28 Allyn Residence VE 1.0 mi @ 152 o /SSE P-38 C Cain Residence VE 14.2 mi @ 359 o /N P-40 C Upstream of Plant BO c 0.4 mi @ 0 o /N P-43 C Peterson Farm WW 13.9 mi. @ 355 o /N
General Area of the Site Boundary
P -01A Property Line TLD 0.4 mi @ 359 o /N P-02A Property Line TLD 0.3 mi @ 10 o /N P-03A Property Line TLD 0.5 mi @ 183 o /S P-04A Property Line TLD 0.4 mi @ 204 o /SSW P-05A Property Line TLD 0.4 mi @ 225 o /SW P-06A Property Line TLD 0.4 mi @ 249 o /WSW P-07A Property Line TLD 0.4 mi @ 268 o /W P-08A Property Line TLD 0.4 mi @ 291 o /WNW P-09A Property Line TLD 0.7 mi @ 317 o /NW P -10A Property Line TLD 0.5 mi @ 333 o /NNW
16 Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued).
Distance and Direction Code Typea Collection Site Sample Typeb from Reactor
Approximately 4 to 5 miles Distant from the Plant
P-01B Thomas Killian Residence TLD 4.7 mi @ 355o/N P-02B Roy Kinneman Residence TLD 4.8 mi @ 17o/NNE P-03B Wayne Anderson Farm TLD 4.9 mi @ 46o/NE P-04B Nelson Drive (Road) TLD 4.2 mi @ 61o/ENE P-05B County Road E and Coulee TLD 4.2 mi @ 102o/ESE P-06B William Hauschildt Residence TLD 4.4 mi @ 112o/ESE P-07B Red Wing Public Works TLD 4.7 mi @ 140o/SE P-08B David Wnuk Residence TLD 4.1 mi @ 165o/SSE P-09B Highway 19 South TLD 4.2 mi @ 187o/S P-10B Cannondale Farm TLD 4.9 mi @ 200o/SSW P-11B Wallace Weberg Farm TLD 4.5 mi @ 221o/SW P-12B Ray Gergen Farm TLD 4.6 mi @ 251o/WSW P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 270o/W P-14B David J. Anderson Farm TLD 4.9 mi @ 306o/NW P-15B Holst Farms TLD 3.8 mi @ 345o/NNW
Special Interest Locations
P-01S Federal Lock & Dam #3 TLD 1.6 mi @ 129 o /SE P-02S Charles Suter Residence TLD 0.5 mi @ 155 o /SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 173 o /S P-04S Richard Burt Residence TLD 2.0 mi @ 202 o /SSW P-05S Kinney Store TLD 2.0 mi @ 270 o /W P-06S Earl Flynn Farm TLD 2.5 mi @ 299 o /WNW P-07S Indian Community TLD 0.7 mi @ 271 o /W P-08S Indian Community TLD 0.7 mi @ 287 o /WNW P-01C C Robert Kinneman Farm TLD 11.1 mi @ 331 o /NNW
17 Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued).
Distance and Direction Code Typea Collection Site Sample Typeb from ISFSI Center.
ISFSI Area Inside Earth Berm
P-01IA ISFSI Nuisance Fence TLD 190' @ 45 o /NE P-02IA ISFSI Nuisance Fence TLD 360' @ 82 o /E P-03IA ISFSI Nuisance Fence TLD 370' @ 100 o /E P-04IA ISFSI Nuisance Fence TLD 200' @ 134 o /SE P-05IA ISFSI Nuisance Fence TLD 180' @ 219 o /SW P-06IA ISFSI Nuisance Fence TLD 320' @ 258 o /WSW P-07IA ISFSI Nuisance Fence TLD 320' @ 281 o /WNW P-08IA ISFSI Nuisance Fence TLD 190' @ 318 o /NW P-01IX ISFSI Nuisance Fence TLD 140' @ 180 o /S P-02IX ISFSI Nuisance Fence TLD 310' @ 270 o /W P-03IX ISFSI Nuisance Fence TLD 140' @ 0 o /N P-04IX ISFSI Nuisance Fence TLD 360' @ 90 o /E
ISFSI Area Outside Earth Berm
P-01IB ISFSI Berm Area TLD 340' @ 3o/N P-02IB ISFSI Berm Area TLD 380' @ 28o/NNE P-03IB ISFSI Berm Area TLD 560' @ 85o/E P-04IB ISFSI Berm Area TLD 590' @ 165o/SSE P-05IB ISFSI Berm Area TLD 690' @ 186o/S P-06IB ISFSI Berm Area TLD 720' @ 201o/SSW P-07IB ISFSI Berm Area TLD 610' @ 271o/W P-08IB ISFSI Berm Area TLD 360' @ 332o/NNW
a "C" type denotes control location. All other locations are indicators.
b Sample Codes:
AP Airborne particulates F Fish AI Airborne Iodine SS Shoreline Sediments BS Bottom (river) sediments SW Surface Water BO Bottom organisms VE Vegetation/vegetables (periphyton or macroinvertebrates) WW Well water DW Drinking water c Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.
18 Table 5.3. Missed collections and analyses at the Prairie Island Nuclear Generating Plant.
All required samples were collected and analyzed with the following exceptions:
Sample Type Analysis Location Collection Reason for not Plan for Date or Conducting REMP Preventing Period as Required Recurrence
Sampler was found with less AP Gross 2 4/20/22 than expected sample time. Power was Beta P-Sample declared missing due restored.
to insufficient running time.
Sampler was found with less AI I-131 P-2 4/20/22 than expected sample time. Power was Sample declared missing due restored.
to insufficient running time.
19 Table 5.4 Radiological Environmental Monitoring Program Summary
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2022
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse
Direct Radiation
TLD (Inner Ring, Gamma 40 3.0 16.6 (40/40) P-06A Property Line 18.5 (4/4) (See Control 0 Area at Site (14.2-19.6) 0.4 mi @ 249° /WSW (17.1-19.5) below.)
Boundary) mR/91 days)
TLD (Outer Ring, Gamma 60 3.0 16.8 (60/60) P-04B, Nelson Drive 20.4 (4/4) (See Control 0 4 -5 mi. distant) (12.5-21.7) 4.2 mi @ 61 o /ENE (19.6-21.4) below.)
mR/91 days)
TLD (Special Gamma 32 3.0 16.2 (32/32) P-04S, Richard Burt, 19.4 (4/4) (See Control 0 Interest Areas) (11.9-20.7) 2.2 mi @ 202° /SSW (18.4-20.0) below.)
mR/91 days)
Gamma 4 3.0 None P -01C, Robert Kinneman 17.5 (4/4) 17.5 (4/4)
TLD (Control) 11.1 mi @ 331° /NNW (16.4-18.6 ) (16.4-18. 6) 0 mR/91 days)
Airborne Pathway Airborne GB 312 0.005 0.030 (260/260) P-06, Air Station 0.032 (52 /52) 0.031 (52/52) 0 Particulates (0.012-0.071) 1.6 mi @ 129° /SE (0.013-0.071) (0.015-0.062)
(pCi/m3)
GS 24 Be-7 0.015 0.082 (20/20) P-07, Air Station 0.087 (4/4) 0.084 (4/4) 0 (0.060-0.110) 0.5 mi @ 271° /W (0.066-0.110) (0.067-0.099)
Mn -54 0.0008 < LLD ) < LLD 0 Co-58 0.0010 < LLD - - < LLD 0 Co-60 0.0009 < LLD - - < LLD 0 Zn-65 0.0027 < LLD - - < LLD 0 Zr-Nb-95 0.0023 < LLD - - < LLD 0 Ru-103 0.0012 < LLD - - < LLD 0 Ru-106 0.0083 < LLD - - < LLD 0 Cs-134 0.0011 < LLD - - < LLD 0 Cs-137 0.0008 < LLD - - < LLD 0 Ba-La-140 0.0049 < LLD - - < LLD 0 Ce-141 0.0023 < LLD - - < LLD 0 Ce-144 0.0045 < LLD - - < LLD 0
Airborne Iodine (pCi/m 3 ) I-131 312 0. 030 < LLD - - < LLD 0
20 Table 5.4 Radiological Environmental Monitoring Program Summary
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306
Location of Facility Goodhue, Minnesota Reporting Period January-December, 2022
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine Analysesa (Units) Rangec Locationd Rangec Rangec Resultse
Terrestrial Pathway
Crops - Cabbage I-131 3 0.034 < LLD - - < LLD 0 (pCi/gwet)
Well Water H-3 20 172 < LLD - - < LLD 0 (pCi/L)
GS 20 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 42 < LLD - - < LLD 0
21 Table 5.4 Radiological Environmental Monitoring Program Summary
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306
Location of Facility Goodhue, Minnesota Reporting Period January-December, 2022
( County, state )
Indicator Location with Highest Control Number Sample Type and Locations Type Number of Mean (F) c Annual Mean Locations Non-Analyses a LLD b Range c Mean (F) c Mean (F) c Routine (Units) Location d Range c Rangec Results e
Waterborne Pathway Drinking Water GB 12 8.9 (12/12) P-11, Red Wing S.C. 8.9 (12/12) None 0 1.0 (6.5-12.1 ) 3.3 mi @ 158° /SSE (6.5-12.1)
(pCi/L)
I-131 12 1.0 < LLD - - None 0 H-3 4 166 < LLD - - None 0 GS 12 - -
Mn-54 10 < LLD - - None 0 Fe-59 30 < LLD - - None 0 Co-58 10 < LLD - - None 0 Co-60 10 < LLD - - None 0 Zn-65 30 < LLD - - None 0 Zr-Nb-95 15 < LLD - - None 0 Cs-134 10 < LLD - - None 0 Cs-137 10 < LLD - - None 0 Ba-La-140 15 < LLD - - None 0 Ce-144 47 < LLD - - None 0
River Water H-3 8 166 < LLD - - < LLD 0
(pCi/L) GS 24
Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 36 < LLD - - < LLD 0 Fish GS 12 (pCi/g wet) K-40 0.10 3.20 (6/6) P-13, U p s t r e a m 3.25 (6/6) 3.25 (6/6) 0 (3.05-3.38) 3.5 mi @ 1 1 3 ° /ESE (2.85-3.55) (2.85-3.55)
Mn-54 0.019 < LLD - - < LLD 0 Fe-59 0.060 < LLD - - < LLD 0 Co-58 0.024 < LLD - - < LLD 0 Co-60 0.021 < LLD - - < LLD 0 Zn-65 0.059 < LLD - - < LLD 0 Zr-Nb-95 0.054 < LLD - - < LLD 0 Cs-134 0.025 < LLD - - < LLD 0 Cs-137 0.020 < LLD - - < LLD 0 Ba-La-140 0.137 < LLD - - < LLD 0
22 Table 5.4 Radiological Environmental Monitoring Program Summary
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesot a Reporting Period January-December 2022
( County, State )
Indicator Location with Highest Control Number
Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse
Waterborne Pathway Invertebrates GS 4
(pCi/g wet)
Be-7 0.24 < LLD - - < LLD 0 K-40 0.37 0.35 (2/2) P-40, Upstream of Plant 0.63 (2/2) 0.63 (2/2) 0 (0.29-0.40) 1.8 mi @ 11° /N (0.62-0.63) (0.62-0.63)
Mn-54 0.015 < LLD - - < LLD 0 Co-58 0.022 < LLD - - < LLD 0 Co-60 0.016 < LLD - - < LLD 0 Zn-65 0.036 < LLD - - < LLD 0 Zr-Nb-95 0.037 < LLD - - < LLD 0 Ru-103 0.028 < LLD - - < LLD 0 Ru-106 0.147 < LLD - - < LLD 0 Cs-134 0.015 < LLD - - < LLD 0 Cs-137 0.017 < LLD - - < LLD 0 Ba-La-140 0.177 < LLD - - < LLD 0 Ce-141 0.053 < LLD - - < LLD 0 Ce-144 0.078 < LLD - - < LLD 0
Bottom and GS 6 Shoreline Sedim ent s Be-7 0.19 < LLD - - < LLD 0 (pCi/g dry) K-40 8.87 (4/4) P-6,Lock and Dam #3 9.23 (2/2) 8.35 (2/2) 0 (8.47-9.91) 1.6 mi @ 129° /SE (8.56-9.91) (7.78-8.93)
Mn-54 0.016 < LLD - - < LLD 0 Co-58 0.021 < LLD - - < LLD 0 Co-60 0.014 < LLD - - < LLD 0 Zn-65 0.037 < LLD - - < LLD 0 Zr-Nb-95 0.034 < LLD - - < LLD 0 Ru-103 0.022 < LLD - - < LLD 0 Ru-106 0.123 < LLD - - < LLD 0 Cs-134 0.015 < LLD - - < LLD 0 Cs-137 0.015 < LLD - - < LLD 0 Ba-La-140 0.079 < LLD - - < LLD 0 Ce-141 0.050 < LLD - - < LLD 0 Ce-144 0.121 < LLD - - < LLD 0
a GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified: (1) by name, and/ or st ation code and (2) by distance (miles) and direction relative t o react or sit e.
e N on-rout ine results are t hose w hich exceed t en t imes t he control st ation value. If no control st ation value is available, t he
result is considered non-routine if it exceeds t en t imes t he t ypical preoperat ional value for t he medium or location.
23
6.0 REFERENCES
CITED
Arnold, J. R. and H. A. Al-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276.
Environmental, Inc., Midwest Laboratory.
2001a through 2021a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2019.
2001b through 2021b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2019.
1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1978 through 1982.
1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -
December, 1978 through 1982.
2022. Quality Manual, Rev. 8, 17 October 2022.
2012. Quality Assurance Program Manual, Rev. 3, 14 November 2012.
2022. Quality Control Procedures Manual, Rev. 5, 9 May 2022.
2009. Quality Control Program, Rev. 2, 12 November 2009.
Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radi onuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.
Northern States Power Company.
1972 through 1974. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1971 to December 31, 1971, 1972, 1973. Minneapolis, Minnesota.
1979 to 2008. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2007. Minneapolis, Minnesota.
Prairie Island Nuclear Generating Plant, 2013. Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.
U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.
24
6.0 REFERENCES
CITED (continued)
U.S. Environmental Protection Agency.
1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).
1984. Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).
2012. RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981 - 2009.
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.
Xcel Energy Corporation.
2009 to 2021. Monticello Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2021. Minneapolis, Minnesota.
2009 to 2021. Prairie Island Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2021.
Minneapolis, Minnesota
25
~~L ATI Environmental, Inc. 'f' /""'\\I Midwest Laboratory
700 L andweh r Road* Northbrook, IL 60062-2310 phone (847) 564-0700
- fax (847) 564-4517
APPENDIX A
INTERLABORATORY AND INTRALABORATORY COMPARISON PROGRAM RESULTS
NOTE: Appendix A is updated four times a year. Th e complete appendix is included in March, June, September and December monthly progress reports only.
January, 2022 through December, 2022
Appendix A
Interlaboratory/ Intralaboratory Comparison Program Results
Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laborato ries. The purpose of such a program is to provide an independent check on a laboratorys analytical procedur es and to alert it of any possible problems.
Participant laboratories measure the concentration of s pecified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
Results in Table A-1 were obtained through participation in the RAD PT Study Proficiency Testing Program administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
Table A-2 lists results for thermoluminescent dosimeters (TLDs), via irradiation and evaluation by the University of W isconsin-Madison Radiation Calibration Laboratory at the University of W isconsin Medical Radiation Research Center.
Table A-3 lists results of the analyses on intralaboratory spiked samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on intralaboratory blank samples for the past twelve months. Data for previous years available upon request.
Table A-5 lists analytical results from the intralaboratory duplicate program for the past twelve months. Acceptance is based on each result being within 25% of the mean of the two results or the two sigma uncertainties of each result overlap.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Results in Table A-7 were obtained through participation in the MRAD PT Study Proficiency Testing Program administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).
Attachment A lists the laboratory acceptance criteria for various analyses.
Out-of-limit results are explained directly below the result.
A-1
Attachment A
ACCEPTANCE CRITERIA FOR INTRALABORATORY SPIKED SAMPLES
Analysis Ratio of lab result to known value.
Gamma Emitters 0.8 to 1.2
Strontium-89, 0.8 to 1.2 Strontium-90
Potassium-40 0.8 to 1.2
Gross alpha 0.5 to 1.5
Gross beta 0.8 to 1.2
Tritium 0.8 to 1.2
Radium-226, 0.7 to 1.3 Radium-228
Plutonium 0.8 to 1.2
Iodine-129, 0.8 to 1.2 Iodine-131
Nickel-63, 0.7 to 1.3 Technetium-99, Uranium-238
Iron-55 0.8 to 1.2
Other Analyses 0.8 to 1.2
A-2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a.
RAD study
Concentration (pCi/L)
Lab Code Date Analysis ERA Laboratory Control Result Result AcceptanceLimits
RAD-128 Study
ERDW -95 1/10/2022 Ba-133 67.4 +/- 4.3 63.0 52.4 - 69.4 Pass ERDW -95 1/10/2022 Cs-134 82.6 +/- 4.1 84.9 69.6 - 93.4 Pass ERDW -95 1/10/2022 Cs-137 35.4 +/- 4.6 29.3 25.2 - 35.3Fail b ERDW -95 1/10/2022 Co-60 104 +/- 4 102 91.8 - 114 Pass ERDW -95 1/10/2022 Zn-65 356 +/- 13 312 281 - 384 Pass ERDW -97 1/10/2022 Gr. Alpha 30.9 +/- 2.2 32.5 16.6 - 42.1 Pass ERDW -97 1/10/2022 Gr. Beta 62.9 +/- 2.3 68.3 47.4 - 75.1 Pass ERDW -99 1/10/2022 Ra-226 8.40 +/- 0.72 9.53 7.14 - 11.1 Pass ERDW -99 1/10/2022 Ra-228 7.25 +/- 2.32 8.71 5.59 - 11.0 Pass ERDW -99 1/10/2022 Uranium 70.9 +/- 2.3 69.0 56.4 - 75.9 Pass ERDW -95 1/10/2022 H-3 23,600 +/- 700 22,200 19,500 - 24,400 Pass
RAD-130 Study
ERDW -2087 8/25/2022 Ba-133 37.2 +/- 3.9 38.2 30.9 - 42.8 Pass ERDW -2087 8/25/2022 Cs-134 81.8 +/- 3.9 88.6 72.7 - 97.5 Pass ERDW -2087 8/25/2022 Cs-137 174 +/- 6 170 153 - 189 Pass ERDW -2087 8/25/2022 Co-60 76.9 +/- 4.0 72.4 65.2 - 82.1 Pass ERDW -2087 8/25/2022 Zn-65 349 +/- 3 326 293 - 380 Pass ERDW -2087 8/25/2022 Gr. Alpha 52.8 +/- 2.4 60.2 31.5 - 74.8 Pass ERDW -2087 8/25/2022 Gr. Beta 18.7 +/- 1.0 17.7 10.1 - 25.9 Pass ERDW -2091 8/25/2022 Ra-226 9.23 +/- 0.57 13.1 9.77 - 15.1Fail c ERDW -2091 8/25/2022 Ra-228 8.72 +/- 1.49 8.40 5.38 - 10.6 Pass ERDW -2095 8/25/2022 H-3 23,900 +/- 481 22,100 19,400 - 24,300 Pass ERDW -2089 8/25/2022 I-131 30.8 +/- 1.0 27.1 23.0 - 32.5 Pass
090622D Study
ERDW -2091 9/6/2022 Ra-226 21.5 +/- 1.1 19.3 14.3 - 22.0Pass c
a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency
testing in drinking water conducted by Environmental Resource Associates (ERA).
b The cesium-137 result did not meet ERA acceptance criteria. It is believed that detector drift could have contributed to
the original Cs-137 result landing outside the upper acceptance limit.
c The radium-226 result did not meet ERA acceptance criteria. An ERA Quick Response PT sample was ordered. The results were
within the acceptance criteria. The reason for the earlier failing result is not known.
A-3
TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).a
mrem Lab Code Irradiation DeliveredReportedb Performancec Date Description Dose DoseQuotient (P)
Environmental, Inc. Group 1
2022-23-1 2/7/2023 Spike 1 134.0 134.5 0.00 2022-23-1 2/7/2023 Spike 2 134.0 131.1 -0.02 2022-23-1 2/7/2023 Spike 3 134.0 134.0 0.00 2022-23-1 2/7/2023 Spike 4 134.0 130.7 -0.02 2022-23-1 2/7/2023 Spike 5 134.0 131.5 -0.02 2022-23-1 2/7/2023 Spike 6 134.0 139.3 0.04 2022-23-1 2/7/2023 Spike 7 134.0 134.8 0.01 2022-23-1 2/7/2023 Spike 8 134.0 130.7 -0.02 2022-23-1 2/7/2023 Spike 9 134.0 133.1 -0.01 2022-23-1 2/7/2023 Spike 10 134.0 129.9 -0.03 2022-23-1 2/7/2023 Spike 11 134.0 125.6 -0.06 2022-23-1 2/7/2023 Spike 12 134.0 139.5 0.04 2022-23-1 2/7/2023 Spike 13 134.0 135.2 0.01 2022-23-1 2/7/2023 Spike 14 134.0 135.8 0.01 2022-23-1 2/7/2023 Spike 15 134.0 133.6 0.00 2022-23-1 2/7/2023 Spike 16 134.0 132.7 -0.01 2022-23-1 2/7/2023 Spike 17 134.0 125.1 -0.07 2022-23-1 2/7/2023 Spike 18 134.0 131.9 -0.02 2022-23-1 2/7/2023 Spike 19 134.0 125.3 -0.06 2022-23-1 2/7/2023 Spike 20 134.0 128.2 -0.04
Mean (Spike 1-20) 132.1 -0.01Passd
Standard Deviation (Spike 1-20) 4.1 0.03Passd
a TLD's were irradiated by the University of W isconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of W isconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.
b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(10)Ka = 1.20. mrem/cGy = 1000.
c Performance Quotient (P) is calculated as ((reported dose - conventionally true value) ÷ conventionally true value) where the conventionally true value is the delivered dose.
d Acceptance is achieved when neither the absolute value of the mean of the P values, nor the standard deviation of the P values exceed 0.15.
A-4 TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).a
mrem Lab Code Irradiation DeliveredReportedb Performancec Date Description Dose DoseQuotient (P)
Environmental, Inc. Group 2
2022-23-2 2/7/2023 Spike 21 70.0 71.7 0.02 2022-23-2 2/7/2023 Spike 22 70.0 72.1 0.03 2022-23-2 2/7/2023 Spike 23 70.0 66.2 -0.05 2022-23-2 2/7/2023 Spike 24 70.0 70.6 0.01 2022-23-2 2/7/2023 Spike 25 70.0 71.0 0.01 2022-23-2 2/7/2023 Spike 26 70.0 71.3 0.02 2022-23-2 2/7/2023 Spike 27 70.0 68.4 -0.02 2022-23-2 2/7/2023 Spike 28 70.0 70.2 0.00 2022-23-2 2/7/2023 Spike 29 70.0 72.1 0.03 2022-23-2 2/7/2023 Spike 30 70.0 71.2 0.02 2022-23-2 2/7/2023 Spike 31 70.0 67.5 -0.04 2022-23-2 2/7/2023 Spike 32 70.0 68.8 -0.02 2022-23-2 2/7/2023 Spike 33 70.0 72.2 0.03 2022-23-2 2/7/2023 Spike 34 70.0 69.6 -0.01 2022-23-2 2/7/2023 Spike 35 70.0 69.7 0.00 2022-23-2 2/7/2023 Spike 36 70.0 68.0 -0.03 2022-23-2 2/7/2023 Spike 37 70.0 72.2 0.03 2022-23-2 2/7/2023 Spike 38 70.0 70.6 0.01 2022-23-2 2/7/2023 Spike 39 70.0 70.4 0.01 2022-23-2 2/7/2023 Spike 40 70.0 66.5 -0.05
Mean (Spike 21-40) 70.0 0.00Passd
Standard Deviation (Spike 21-40) 1.9 0.03Passd
a TLD's were irradiated by the University of W isconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of W isconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.
b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(10)Ka = 1.20. mrem/cGy = 1000.
c Performance Quotient (P) is calculated as ((reported dose - conventionally true value) ÷ conventionally true value) where the conventionally true value is the delivered dose.
d Acceptance is achieved when neither the absolute value of the mean of the P values, nor the standard deviation of the P values exceed 0.15.
A-5 TABLE A-3. Intralaboratory "Spiked" Samples
Concentrationa Lab Codeb Date Analysis Known RatioLaboratory resultsControl 2s, n=1c Activity Acceptance Lab/KnownLimitsd
SPDW -30305 1/5/2022 Gr. Alpha 3.9 +/- 0.8 6.3 3.1 - 9.4 Pass 0.62 SPDW -30305 1/5/2022 Gr. Beta 65.5 +/- 1.6 75.9 60.7 - 91.1 Pass 0.86 SPDW -40000 1/7/2022 H-3 2,220 +/- 162 2,110 1,688 - 2,532 Pass 1.05 SPDW -40013 1/6/2022 Ra-226 12.7 +/- 0.3 12.3 8.6 - 16.0 Pass 1.03 SPDW -40014 7/12/2021 H-3 11,681 +/- 345 10,400 8,320 - 12,480 Pass 1.12 SPDW -40015 7/12/2021 H-3 11,318 +/- 340 10,400 8,320 - 12,480 Pass 1.09
SPDW -40022 2/3/2022 Ra-228 14.5 +/- 3.9 15.3 10.7 - 19.9 Pass 0.95 SPDW -40024 2/4/2022 H-3 10,502 +/- 321 10,400 8,320 - 12,480 Pass 1.01 SPDW -40025 1/11/2021 H-3 2,278 +/- 176 2,110 1,688 - 2,532 Pass 1.08 SPDW -40026 1/11/2021 H-3 2,291 +/- 176 2,110 1,688 - 2,532 Pass 1.09 SPDW -40028 2/11/2022 H-3 10,594 +/- 322 10,400 8,320 - 12,480 Pass 1.02 SPDW -40037 2/25/2022 H-3 10,724 +/- 322 10,400 8,320 - 12,480 Pass 1.03
SPDW -40045 3/3/2022 Sr-90 19.2 +/- 1.1 17.1 13.7 - 20.5 Pass 1.12 SPDW -40052 3/10/2022 H-3 10,851 +/- 328 10,400 8,320 - 12,480 Pass 1.04 SPDW -40064 3/18/2022 H-3 10,795 +/- 332 10,400 8,320 - 12,480 Pass 1.04 SPDW -40073 3/22/2022 Ra-228 15.1 +/- 2.4 13.4 9.4 - 17.4 Pass 1.13 SPDW -40075 1/28/2022 Ra-226 12.2 +/- 0.3 12.3 8.6 - 16.0 Pass 0.99 SPDW -40078 3/14/2022 U-234 28.0 +/- 2.0 23.0 16.1 - 29.9 Pass 1.22 SPDW -40078 3/14/2022 U-238 29.9 +/- 2.1 23.2 16.2 - 30.2 Pass 1.29 SPW -598 3/24/2022 Fe-55 10,505 +/- 1,100 10,006 8005 - 12,007 Pass 1.05 SPDW -40087 3/24/2022 Ra-226 14.4 +/- 0.4 12.3 8.6 - 16.0 Pass 1.17 LCS-W -032222 1/10/2022 Ba-133 65.4 +/- 6.5 63.0 50 - 76 Pass 1.04 LCS-W -032222 1/10/2022 Cs-134 87.7 +/- 6.0 84.9 68 - 102 Pass 1.03 LCS-W -032222 1/10/2022 Cs-137 34.2 +/- 6.6 29.3 23 - 35 Pass 1.17 LCS-W -032222 1/10/2022 Co-60 106 +/- 6 102 82 - 122 Pass 1.04 LCS-W -032222 1/10/2022 Zn-65 341 +/- 18 312 250 - 374 Pass 1.09
SPDW -40083 4/1/2022 H-3 10,785 +/- 329 10,400 8,320 - 12,480 Pass 1.04 LCS-W -040622 1/10/2022 Ba-133 60.4 +/- 7.6 63.0 50.4 - 75.6 Pass 0.96 LCS-W -040622 1/10/2022 Cs-134 91.4 +/- 6.8 84.9 67.9 - 102 Pass 1.08 LCS-W -040622 1/10/2022 Cs-137 31.7 +/- 8.5 29.3 23.4 - 35.2 Pass 1.08 LCS-W -040622 1/10/2022 Co-60 111 +/- 7 102 81.6 - 122 Pass 1.08 LCS-W -040622 1/10/2022 Zn-65 330 +/- 28 312 250 - 374 Pass 1.06 LCS-SO-040822 8/1/2020 Cs-134 17,126 +/- 176 19,189 15,351 - 23,027 Pass 0.89 LCS-SO-040822 8/1/2020 Co-57 29,070 +/- 356 29,730 23,784 - 35,676 Pass 0.98 LCS-SO-040822 8/1/2020 Co-60 27,057 +/- 166 27,027 21,622 - 32,432 Pass 1.00 LCS-SO-040822 8/1/2020 Mn-54 17,886 +/- 455 16,486 13,189 - 19,783 Pass 1.08 LCS-SO-040822 8/1/2020 K-40 18,799 +/- 685 16,810 13,448 - 20,172 Pass 1.12 LCS-SO-040822 8/1/2020 Zn-65 14,460 +/- 754 12,703 10,162 - 15,244 Pass 1.14 SPDW -40085 4/4/2022 Sr-90 17.3 +/- 1.1 17.1 13.7 - 20.5 Pass 1.01 SPDW -40089 4/8/2022 H-3 10,677 +/- 326 10,400 8,320 - 12,480 Pass 1.03 SPDW -40130 4/8/2022 Ra-226 11.4 +/- 0.3 12.3 8.6 - 16.0 Pass 0.93 SPDW -40098 4/11/2022 Gr. Alpha 6.7 +/- 1.1 6.3 3.1 - 9.4 Pass 1.07 SPDW -40098 4/11/2022 Gr. Beta 71.7 +/- 1.7 75.9 60.7 - 91.1 Pass 0.94 SPDW -40102 4/14/2022 H-3 10,369 +/- 323 10,400 8,320 - 12,480 Pass 1.00
a Liquid sample results are reported in pCi/ Liter, air filters ( pCi/m3), charcoal (p Ci/charcoal canister), and solid samples (pC i/kg).
b Laboratory codes : W & SPW (W ate r), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (c harcoal canister), F (fish), U (urine).
c Results are based on single determinations.
d Acceptance criteria are listed in Attachment A of this report.
A-6 TABLE A-3. Intralaboratory "Spiked" Samples
Concentration a Lab Codeb Date Analysis Known RatioLaboratory resultsControl
2s, n=1c Activity Acceptance Lab/KnownLimitsd
SPDW -40132 5/3/2022 H-3 10,834 +/- 329 10,400 8,320 - 12,480 Pass 1.04 SPDW -40142 5/5/2022 Ra-226 11.6 +/- 0.4 12.3 8.6 - 16.0 Pass 0.94 SPDW -40139 5/18/2022 H-3 10,465 +/- 322 10,400 8,320 - 12,480 Pass 1.01 SPDW -40147 5/9/2022 Gr. Alpha 22.1 +/- 1.2 32.5 16.3 - 48.8 Pass 0.68 SPDW -40132 5/3/2022 H-3 10,834 +/- 329 10,400 8,320 - 12,480 Pass 1.04 SPDW -40142 5/5/2022 Ra-226 11.6 +/- 0.4 12.3 8.6 - 16.0 Pass 0.94 SPDW -40139 5/18/2022 H-3 10,465 +/- 322 10,400 8,320 - 12,480 Pass 1.01 SPDW -40147 5/9/2022 Gr. Alpha 22.1 +/- 1.2 32.5 16.3 - 48.8 Pass 0.68 SPDW -40147 5/9/2022 Gr. Beta 63.1 +/- 1.6 62.9 50.3 - 75.5 Pass 1.00 SPDW -40157 5/25/2022 Ra-226 10.1 +/- 0.3 12.3 8.6 - 16.0 Pass 0.82
SPW -1856 6/14/2022 Sr-90 17.4 +/- 2.9 17.1 13.7 - 20.5 Pass 1.02 LCS-AP-061522 3/21/2022 Cs-134 479 +/- 10 549 439 - 659 Pass 0.87 LCS-AP-061522 3/21/2022 Cs-137 1,418 +/- 117 1,320 1,056 - 1,584 Pass 1.07 LCS-AP-061522 3/21/2022 Co-60 891 +/- 8 885 708 - 1,062 Pass 1.01 LCS-AP-061522 3/21/2022 Zn-65 769 +/- 18 671 537 - 805 Pass 1.15 SPDW -40164 6/21/2022 Ra-228 14.2 +/- 1.8 13.4 9.4 - 17.4 Pass 1.06 SPDW -40167 6/23/2022 H-3 10,497 +/- 322 10,400 8,320 - 12,480 Pass 1.01 SPDW -40177 6/30/2022 Ra-226 12.1 +/- 0.3 12.3 8.6 - 16.0 Pass 0.98 SPW -1881 6/27/2022 Tc-99 97.1 +/- 1.7 107.8 75.5 - 140.1 Pass 0.90
SPDW -40253 7/12/2022 Ra-226 11.6 +/- 0.3 12.3 8.6 - 16.0 Pass 0.94 SPW -40179 7/15/2022 H-3 10,467 +/- 324 10,400 8,320 - 12,480 Pass 1.01 SPDW -40200 7/26/2022 Gr. Alpha 21.1 +/- 1.3 32.5 16.3 - 48.8 Pass 0.65 SPDW -40200 7/26/2022 Gr. Beta 61.0 +/- 1.6 62.9 50.3 - 75.5 Pass 0.97 SPDW -40220 7/29/2022 H-3 10,553 +/- 326 10,400 8,320 - 12,480 Pass 1.01
SPDW -40212 8/9/2022 Ra-228 14.5 +/- 2.3 13.4 9.4 - 17.4 Pass 1.08 SPDW -40220 8/16/2022 H-3 10,613 +/- 326 10,400 8,320 - 12,480 Pass 1.02 SPDW -40239 8/22/2022 Gr. Alpha 37.1 +/- 2.0 60.2 31.5 - 74.8 Pass 0.62 SPDW -40239 8/22/2022 Gr. Beta 16.6 +/- 0.9 17.7 10.1 - 25.9 Pass 0.94 SPDW -40255 8/12/2022 Ra-226 9.1 +/- 0.3 12.3 8.6 - 16.0 Pass 0.74
SPDW -40265 9/2/2022 H-3 10,555 +/- 325 10,400 8,320 - 13,520 Pass 1.01 SPDW -40267 9/6/2022 Ra-228 14.0 +/- 1.4 13.4 9.4 - 17.4 Pass 1.04 SPDW -40283 9/9/2022 H-3 10,059 +/- 318 10,400 8,320 - 12,480 Pass 0.97 SPDW -40300 8/31/2022 Ra-226 11.2 +/- 0.3 12.3 8.6 - 16.0 Pass 0.91 SPMI-2918 9/19/2022 Sr-90 17.9 +/- 1.0 17.1 13.7 - 20.5 Pass 1.05 SPDW -40321 9/20/2022 Ra-226 13.2 +/- 0.5 12.3 8.6 - 16.0 Pass 1.07 SPDW -40305 9/21/2022 Ra-228 12.5 +/- 1.8 13.4 9.4 - 17.4 Pass 0.93 SPDW -40294 9/20/2022 Gr. Alpha 35.1 +/- 2.0 60.2 31.5 - 74.8 Pass 0.58 SPDW -40294 9/20/2022 Gr. Beta 16.5 +/- 1.0 17.7 10.1 - 25.9 Pass 0.93 SPDW -40303 9/19/2022 H-3 10,078 +/- 316 10,400 8,320 - 12,480 Pass 0.97 SPDW -40361 10/12/2022 Ra-226 10.0 +/- 0.3 12.3 8.6 - 16.0 Pass 0.81
a Liquid sample results are reported in pCi/Li ter, air filters ( pCi/m3), charcoal (pCi/charcoal cani ster), and solid samples (pC i/kg).
b Laboratory codes : W & SPW (W ater), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (c harcoal canister), F (fish), U (urine).
c Results are based on single determinations.
d Acceptance criteria are listed in Attachment A of this report.
A-7 TABLE A-3. Intralaboratory "Spiked" Samples
Concentration a Lab Codeb Date Analysis Known RatioLaboratory resultsControl 2s, n=1c Activity Acceptance Lab/KnownLimitsd
SPDW -40344 11/3/2022 Ra-228 13.2 +/- 1.8 13.4 9.4 - 17.4 Pass 0.99 SPDW -40346 11/8/2022 Gr. Alpha 42.0 +/- 2.2 60.2 31.5 - 74.8 Pass 0.70 SPDW -40346 11/8/2022 Gr. Beta 16.6 +/- 1.0 17.7 10.1 - 25.9 Pass 0.94 SPDW -40352 11/17/2022 Sr-90 18.8 +/- 1.2 17.1 13.7 - 20.5 Pass 1.10 SPDW -40355 11/18/2022 H-3 10,143 +/- 316 10,400 8,320 - 12,480 Pass 0.98 SPDW -40364 11/30/2022 Gr. Alpha 38.4 +/- 1.5 60.2 31.5 - 74.8 Pass 0.64 SPDW -40364 11/30/2022 Gr. Beta 30.9 +/- 1.2 17.7 10.1 - 25.9 Pass 1.75 LCS-W -110822 2/1/2022 Cs-137 222 +/- 10 206 165 - 247 Pass 1.08 LCS-W -110822 2/1/2022 Co-57 1,060 +/- 117 973 778 - 1,168 Pass 1.09 LCS-W -110822 2/1/2022 Co-60 250 +/- 8 251 201 - 301 Pass 1.00 LCS-W -110822 2/1/2022 Mn-54 537 +/- 18 511 409 - 613 Pass 1.05 LCS-W -110822 2/1/2022 Zn-65 673 +/- 35 708 566 - 850 Pass 0.95
SPDW -40372 11/21/2022 Ra-226 11.3 +/- 0.3 12.3 8.6 - 16.0 Pass 0.92 SPU-3883 12/1/2022 H-3 21,694 +/- 1, 387 23,900 19,120 - 28,680 Pass 0.91 SPW -3950 12/1/2022 Ni-63 1,937 +/- 28 2,135.0 1,495 - 2,776 Pass 0.91 SPDW -40366 12/2/2022 H-3 22,466 +/- 46 4 23,900 19,120 - 28,680 Pass 0.94 SPW -3969 12/2/2022 Ni-63 2,123 +/- 29 2,135.0 1,495 - 2,776 Pass 0.99 SPW -3881 12/5/2022 Tc-99 85.0 +/- 1.6 107.8 75.5 - 140.1 Pass 0.79 SPDW -40374 12/12/2022 H-3 22,554 +/- 463 23,900 19,120 - 28,680 Pass 0.94 SPDW -40382 12/12/2022 Ra-226 12.7 +/- 0.4 12.3 8.6 - 16.0 Pass 1.03 SPDW -40380 12/22/2022 H-3 22,200 +/- 462 23,900.0 19,120 - 28,680 Pass 0.93
a Liquid sample results are reported in pCi/Li ter, air filters ( pCi/m3), charcoal (pCi/charcoal canist er), and solid samples (pC i/kg).
b Laboratory codes : W & SPW (W ater), MI (milk ), AP (air filter), SO (soil), VE (vegetati on), CH (charcoal cani ster), F (fish), U (urine).
c Results are based on single determinations.
d Acceptance criteria are listed in Attachment A of this report.
A-8 TABLE A-4. Intralaboratory "Blank" Samples
Concentrationa Lab Codeb Sample Date Analysisc Laboratory results (4.66 V ) Acceptance Type LLDActivitydCriteria (4.66 V )
SPDW -30304 W ater 1/5/2022 Gr. Alpha 0.47 0.07 +/- 0.33 2 SPDW -30304 W ater 1/5/2022 Gr. Beta 0.77 0.33 +/- 0.55 4 SPDW -40001 W ater 1/7/2022 H-3 156 3 +/- 75 200 SPDW -40012 W ater 1/6/2022 Ra-226 0.06 -0.08 +/- 0.05 2 SPDW -40016 W ater 7/12/2021 H-3 165 -41 +/- 85 200 SPDW -40017 W ater 7/21/2021 H-3 165 0 +/- 87 200
SPDW -40021 W ater 2/3/2022 Ra-228 1.15 0.20 +/- 0.56 2 SPDW -40023 W ater 2/4/2022 H-3 162 78 +/- 81 200 SPDW -40027 W ater 2/11/2022 H-3 168 26 +/- 85 200 SPDW -40036 W ater 2/25/2022 H-3 160 55 +/- 78 200
SPDW -40044 W ater 3/3/2022 Sr-89 0.62 0.20 +/- 0.44 5 SPDW -40044 W ater 3/3/2022 Sr-90 0.60 -0.18 +/- 0.26 1 SPDW -40046 W ater 3/3/2022 I-131 0.12 0.04 +/- 0.08 1 SPDW -40051 W ater 3/10/2022 H-3 161 17 +/- 78 200 SPDW -40063 W ater 3/18/2022 H-3 177 60 +/- 96 200 SPDW -40072 W ater 3/22/2022 Ra-228 1.20 0.29 +/- 0.56 2 SPDW -40074 W ater 1/28/2022 Ra-226 0.06 0.08 +/- 0.14 2 SPDW -40077 W ater 3/14/2022 U-234 0.19 0.17 +/- 0.20 1 SPDW -40077 W ater 3/14/2022 U-238 0.19 -0.04 +/- 0.14 1 SPW -597 W ater 3/31/2022 Fe-55 1159 92 +/- 708 2000 SPDW -40081 W ater 3/30/2022 Ra-228 1.66 0.19 +/- 0.79 2
SPDW -40082 W ater 4/1/2022 H-3 170 60 +/- 85 200 SPDW -40084 W ater 4/4/2022 Sr-89 0.51 0.28 +/- 0.41 5 SPDW -40084 W ater 4/4/2022 Sr-90 0.55 0.01 +/- 0.25 1 SPDW -40088 W ater 4/8/2022 H-3 166.00 66.00 +/- 83.00 200 SPDW -40129 W ater 4/8/2022 Ra-226 0.01 0.11 +/- 0.02 2 SPDW -40098 W ater 4/11/2022 Gr. Alpha 0.42 0.06 +/- 0.30 2 SPDW -40098 W ater 4/11/2022 Gr. Beta 0.75 -0.73 +/- 0.50 4 SPDW -40101 W ater 4/14/2022 H-3 164 37 +/- 84 200 SPDW -40120 W ater 4/22/2022 H-3 109 74 +/- 84 200
SPDW -40131 W ater 5/3/2022 H-3 165 75 +/- 86 200 SPDW -40141 W ater 5/5/2022 Ra-226 0.08 0.01 +/- 0.07 2 SPU-1297 Urine 5/12/2022 H-3 1325 674 +/- 733 200 SPDW -40138 W ater 5/18/2022 H-3 163 69 +/- 80 200 SPDW -40156 W ater 5/25/2022 Ra-226 0.04 0.09 +/- 0.03 2
SPW -1855 W ater 6/14/2022 Sr-89 0.63 0.02 +/- 0.49 5 SPW -1855 W ater 6/14/2022 Sr-90 0.57 0.00 +/- 0.26 1 SPDW -40172 W ater 6/14/2022 Ra-226 0.03 0.06 +/- 0.03 2 SPDW -40163 W ater 6/21/2022 Ra-228 0.84 0.30 +/- 0.43 2 SPDW -40166 W ater 6/23/2022 H-3 162 46 +/- 78 200 SPW -1876 W ater 6/27/2022 C-14 9.99 -9.14 +/- 5.92 200
a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b Laboratory codes : W & SPW (W ater), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).
c I-131(G); iodine-131 as analyzed by gamma spectroscopy.
d Activity reported is a net activity result.
A-9 TABLE A-4. Intralaboratory "Blank" Samples
Concentration a Lab Codeb Sample Date Analysisc Laboratory results (4.66 V ) Acceptance Type LLDActivitydCriteria (4.66 V )
SPW -1878 W ater 6/27/2022 Fe-55 522 -200 +/- 306 2000 SPW -1880 W ater 6/27/2022 Tc-99 11.4 -6.0 +/- 6.8 200 SPW -1891 W ater 6/28/2022 Ni-63 75.9 0.0 +/- 46.1 200 SPDW -40176 W ater 6/30/2022 Ra-226 0.04 0.06 +/- 0.04 2
SPDW -40252 W ater 7/12/2022 Ra-226 0.04 -0.06 +/- 0.10 2 SPDW -40178 W ater 7/15/2022 H-3 167 58 +/- 83 200 SPW -2220 W ater 7/21/2022 C-14 3.52 -3.15 +/- 2.09 200 SPDW -40199 W ater 7/26/2022 Gr. Alpha 0.80 0.47 +/- 0.58 2 SPDW -40199 W ater 7/26/2022 Gr. Beta 0.77 0.98 +/- 0.57 4 SPDW -40207 W ater 7/29/2022 H-3 161 -21 +/- 84 200
SPDW -40211 W ater 8/9/2022 Ra-228 1.23 0.20 +/- 0.59 2 SPDW -40219 W ater 8/16/2022 H-3 161 68 +/- 80 200 SPDW -40238 W ater 8/22/2022 Gr. Alpha 0.47 0.05 +/- 0.34 2 SPDW -40238 W ater 8/22/2022 Gr. Beta 0.75 0.34 +/- 0.54 4
SPDW -40263 W ater 9/2/2022 I-131 0.17 -0.05 +/- 0.09 1 SPDW -40264 W ater 9/2/2022 H-3 162 82 +/- 81 200 SPDW -40264 W ater 9/6/2022 Ra-228 1.11 -0.22 +/- 0.49 2 SPDW -40282 W ater 9/9/2022 H-3 163 71 +/- 83 200 SPDW -40291 W ater 9/16/2022 I-131 0.11 -0.01 +/- 0.08 1 SPMI-2917 Milk 9/19/2022 Sr-89 0.58 0.03 +/- 0.47 5 SPMI-2917 Milk 9/19/2022 Sr-90 0.51 0.30 +/- 0.27 1 SPDW -40293 W ater 9/20/2022 Gr. Alpha 0.52 0.10 +/- 0.37 2 SPDW -40293 W ater 9/20/2022 Gr. Beta 0.78 0.26 +/- 0.55 4 SPDW -40302 W ater 9/19/2022 H-3 160 97 +/- 80 200 SPDW -40304 W ater 9/21/2022 Ra-228 0.87 0.09 +/- 0.41 2 SPDW -40311 W ater 9/30/2022 I-131 0.15 0.00 +/- 0.08 1
SPDW -40345 W ater 11/8/2022 Gr. Alpha 0.53 -0.17 +/- 0.36 2 SPDW -40345 W ater 11/8/2022 Gr. Beta 0.78 -0.05 +/- 0.54 4 SPDW -40350 W ater 11/11/2022 H-3 166 96 +/- 84 200 SPDW -40352 W ater 11/17/2022 Sr-89 0.66 -0.01 +/- 0.53 5 SPDW -40352 W ater 11/17/2022 Sr-90 0.61 0.11 +/- 0.29 1 SPDW -40354 W ater 11/18/2022 H-3 155 21 +/- 76 200 SPDW -40354 W ater 11/18/2022 I-131 0.18 -0.11 +/- 0.09 1
SPW -3880 W ater 12/1/2022 Tc-99 5.58 2.99 +/- 3.44 200 SPU-3882 Urine 12/1/2022 H-3 1157 599 +/- 642 2000 SPW -3949 W ater 12/2/2022 Ni-63 16.3 9.0 +/- 10.0 200 SPW -3968 W ater 12/2/2022 Ni-63 15.9 0.0 +/- 9.6 200 SPDW -40370 W ater 12/7/2022 I-131 0.10 -0.04 +/- 0.06 1 SPDW -40381 Ra-226 12/12/2022 Ra-226 0.06 -0.04 +/- 0.05 2 SPDW -40379 H-3 12/22/2022 H-3 162 107 +/- 84 200
a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b Laboratory codes : W & SPW (W ater), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).
c I-131(G); iodine-131 as analyzed by gamma spectroscopy.
d Activity reported is a net activity result.
A-10 TABLE A-5. Intralaborator y "Duplicate" Samples
Concentrationa Averaged Lab Codeb Date Analysis AcceptanceFirst ResultSecond ResultResult
CF-20,21 1/3/2022 Gr. Beta 7.07 +/- 0.26 7.05 +/- 0.26 7.06 +/- 0.18 Pass CF-20,21 1/3/2022 K-40 9.06 +/- 0.28 7.54 +/- 0.70 8.30 +/- 0.38 Pass U-135,136 1/20/2022 Beta (-K40) 5.74 +/- 1.63 3.53 +/- 1.40 4.64 +/- 1.07 Pass DW -40019,40020 1/25/2022 Gr. Alpha 5. 01 +/- 1.34 6.01 +/- 1.40 5.51 +/- 0.97 Pass DW -40019,40020 1/25/2022 Ra-226 1.19 +/- 0.15 0.98 +/- 0.17 1.09 +/- 0.11 Pass DW -40019,40020 1/25/2022 Ra-228 4.84 +/- 0.98 5.38 +/- 1.05 5.11 +/- 0.72 Pass W -159,160 1/27/2022 Gr. Alpha 3.04 +/- 3.19 3.85 +/- 2.04 3.45 +/- 1.89 Pass W -159,160 1/27/2022 Gr. Beta 14.4 +/- 2.7 13.1 +/- 1.5 13.7 +/- 1.5 Pass W -159,160 1/27/2022 Ra-226 0.94 +/- 0.19 1.11 +/- 0.30 1.03 +/- 0.18 Pass W -159,160 1/27/2022 Ra-228 3.14 +/- 0.96 3.39 +/- 0.96 3.27 +/- 0.68 Pass
W -888,889 2/14/2022 Ni-63 119 +/- 47 95 +/- 48 107 +/- 34 Pass S-391,392 2/17/2022 K-40 11.2 +/- 0.8 9.8 +/- 0.7 10.5 +/- 0.5 Pass DW -40040,40041 2/25/2022 Ra-226 2.78 +/- 0.21 2.01 +/- 0.22 2.40 +/- 0.15 Pass DW -40040,40041 2/25/2022 Ra-228 3.15 +/- 0.95 3.29 +/- 0.94 3.22 +/- 0.67 Pass AP-022821A,B 2/28/2022 Gr. Beta 0.038 +/- 0.005 0.039 +/- 0.005 0.039 +/- 0.003 Pass
S-435,436 3/2/2022 Pb-214 1.42 +/- 0.11 1.29 +/- 0.15 1.36 +/- 0.09 Pass S-435,436 3/2/2022 Ac-228 0.94 +/- 0.20 1.06 +/- 0.15 1.00 +/- 0.13 Pass AP-030721A,B 3/7/2022 Gr. Beta 0.038 +/- 0.005 0.038 +/- 0.005 0.038 +/- 0.004 Pass S-477,478 3/8/2022 K-40 6.58 +/- 0.23 6.73 +/- 0.24 6.66 +/- 0.17 Pass SW T-657,658 3/9/2022 Gr. Beta 1.00 +/- 0.54 1.20 +/- 0.57 1.10 +/- 0.39 Pass DW -40059,40060 3/11/2022 Ra-226 0.40 +/- 0.10 0.53 +/- 0.11 0.47 +/- 0.07 Pass DW -40059,40060 3/11/2022 Ra-228 0.40 +/- 0.60 0.72 +/- 0.60 0.56 +/- 0.42 Pass AP-0315221A,B 3/15/2022 Gr. Beta 0.025 +/- 0.003 0.027 +/- 0.003 0.026 +/- 0.002 Pass AP-1161,1162 3/29/2022 Be-7 0.07 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 Pass
DW -700,701 4/4/2022 Gr. Alpha 1.70 +/- 1.83 2.82 +/- 1.78 2.26 +/- 1.28 Pass DW -700,701 4/4/2022 Gr. Beta 3.33 +/- 1.26 4.29 +/- 1.30 3.81 +/- 0.91 Pass DW -700,701 4/4/2022 Ra-226 0.50 +/- 0.16 0.65 +/- 0.14 0.58 +/- 0.11 Pass DW -700,701 4/4/2022 Ra-228 5.04 +/- 1.00 4.79 +/- 0.99 4.92 +/- 0.70 Pass SG-706,707 4/4/2022 Gr. Alpha 25.7 +/- 3.6 21.7 +/- 3.2 23.7 +/- 2.4 Pass SG-706,707 4/4/2022 Gr. Beta 23.2 +/- 1.7 24.5 +/- 1.8 23.9 +/- 1.3 Pass SG-706,707 4/4/2022 Ra-226 2.47 +/- 0.10 2.62 +/- 0.09 2.55 +/- 0.07 Pass SG-706,707 4/4/2022 Ra-228 4.63 +/- 0.22 4.40 +/- 0.20 4.52 +/- 0.15 Pass DW -40091,40092 4/5/2022 Gr. Alpha 0. 43 +/- 0.78 0.57 +/- 0.82 0.50 +/- 0.57 Pass DW -40091,40092 4/6/2022 Ra-226 0.21 +/- 0.10 0.24 +/- 0.08 0.23 +/- 0.06 Pass U-951,952 4/13/2022 Gr. Beta 2. 72 +/- 1.55 4.11 +/- 1.45 3.41 +/- 1.06 Pass U-951,952 4/13/2022 H-3 861 +/- 723 1,015 +/- 732 938 +/- 514 Pass W -1014,1015 4/21/2022 Ra-228 1.76 +/- 0.93 1.51 +/- 0.92 1.64 +/- 0.65 Pass W -1014,1015 4/21/2022 Ra-226 1.23 +/- 0.27 1.36 +/- 0.29 1.30 +/- 0.20 Pass DW -40117,40118 4/26/2022 Ra-226 0.33 +/- 0.22 0.29 +/- 0.09 0.31 +/- 0.12 Pass SW -1034,1035 4/26/2022 H-3 15,159 +/- 386 16,022 +/- 396 15,591 +/- 277 Pass DW -40124,40125 4/28/2022 Gr. Alpha 0. 70 +/- 0.56 0.60 +/- 0.68 0.65 +/- 0.44 Pass
A-11 TABLE A-5. Intralaborato ry "Duplicate" Samples
Concentration a Averaged Lab Codeb Date Analysis AcceptanceFirst ResultSecond ResultResult
SO-1266,1267 5/9/2022 K-40 17.7 +/- 0.8 16.0 +/- 1.0 16.8 +/- 0.6 Pass SO-1266,1267 5/9/2022 Pb-214 0.42 +/- 0.05 0.30 +/- 0.06 0.36 +/- 0.04 Pass SO-1266,1267 5/9/2022 Ac-228 0.58 +/- 0.09 0.61 +/- 0.02 0.60 +/- 0.05 Pass AP-51721,51722 5/17/2022 Gr. Beta 0.023 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.002 Pass SG-1368,1369 5/18/2022 Pb-214 4.31 +/- 0.27 5.78 +/- 0.31 5.05 +/- 0.21 Pass SG-1368,1369 5/18/2022 Ac-228 6.08 +/- 0.56 6.59 +/- 0.50 6.34 +/- 0.38 Pass SG-1368,1369 5/18/2022 Gr. Alpha 37.8 +/- 1.7 40.6 +/- 1.7 39.2 +/- 1.2 Pass SG-1368,1369 5/18/2022 Gr. Beta 34.8 +/- 0.8 31.2 +/- 0.8 33.0 +/- 0.6 Pass DW -40143,40144 5/19/2022 Ra-226 1.17 +/- 0.25 1.56 +/- 0.16 1.37 +/- 0.15 Pass DW -40143,40144 5/19/2022 Ra-228 1.29 +/- 0.72 2.14 +/- 0.85 1.72 +/- 0.56 Pass AP-53121,53122 5/31/2022 Gr. Beta 0.016 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.002 Pass
PM-1646,1647 6/1/2022 K-40 14.2 +/- 0.8 13.9 +/- 0.4 14.1 +/- 0.5 Pass S-1731,1732 6/6/2022 K-40 16.5 +/- 0.8 15.8 +/- 1.9 16.2 +/- 1.0 Pass DW -40152,40153 6/7/2022 Gr. Alpha 4.00 +/- 0.74 3.50 +/- 0.70 3.75 +/- 0.51 Pass AP-60721,60722 6/7/2022 Gr. Beta 0.014 +/- 0.003 0.013 +/- 0.003 0.013 +/- 0.002 Pass S-1773,1774 6/13/2022 Be-7 1.29 +/- 0.28 1.56 +/- 0.15 1.43 +/- 0.16 Pass S-1773,1774 6/13/2022 K-40 13.8 +/- 0.7 13.3 +/- 0.7 13.6 +/- 0.5 Pass AP-61321,61322 6/13/2022 Gr. Beta 0.023 +/- 0.004 0.023 +/- 0.004 0.023 +/- 0.003 Pass AP-62021,62022 6/20/2022 Gr. Beta 0.031 +/- 0.005 0.031 +/- 0.005 0.031 +/- 0.003 Pass AP-62721,62722 6/27/2022 Gr. Beta 0.027 +/- 0.005 0.027 +/- 0.005 0.027 +/- 0.003 Pass DW -40169,40170 6/29/2022 Ra-228 1.06 +/- 0.70 0.17 +/- 0.54 0.62 +/- 0.44 Pass DW -40169,40170 6/29/2022 Ra-226 0.22 +/- 0.12 0.03 +/- 0.12 0.13 +/- 0.08 Pass
W -2014,2015 7/4/2022 Ra-226 0.73 +/- 0.24 0.72 +/- 0.27 0.73 +/- 0.18 Pass S-2035,2036 7/7/2022 Pb-214 1.00 +/- 0.09 1.65 +/- 0.11 1.33 +/- 0.07 Pass S-2035,2036 7/7/2022 Ac-228 1.16 +/- 0.20 1.09 +/- 0.18 1.13 +/- 0.13 Pass S-2152,2153 7/13/2022 Pb-214 0.58 +/- 0.07 0.65 +/- 0.05 0.62 +/- 0.04 Pass S-2152,2153 7/13/2022 Ac-228 0.62 +/- 0.11 0.61 +/- 0.08 0.62 +/- 0.07 Pass S-2152,2153 7/18/2022 K-40 10.9 +/- 0.8 12.5 +/- 0.8 11.7 +/- 0.6 Pass DW -40192,40193 7/19/2022 Ra-226 0.80 +/- 0.10 0.70 +/- 0.10 0.75 +/- 0.07 Pass DW -40192,40193 7/19/2022 Ra-228 0.03 +/- 0.60 1.20 +/- 0.68 0.62 +/- 0.45 Pass DW -40205,40206 7/27/2022 Ra-226 0.32 +/- 0.15 0.28 +/- 0.10 0.30 +/- 0.09 Pass DW -40205,40206 7/27/2022 Ra-228 0.34 +/- 0.59 0.65 +/- 0.62 0.50 +/- 0.43 Pass
G-2343,2344 8/1/2022 Be-7 3.00 +/- 0.31 3.04 +/- 0.26 3.02 +/- 0.20 Pass G-2343,2344 8/1/2022 K-40 5.82 +/- 0.53 6.03 +/- 0.39 5.93 +/- 0.33 Pass W -2406,2407 8/1/2022 Gr. Alpha 4.27 +/- 3.20 4.60 +/- 2.95 4.44 +/- 2.18 Pass W -2406,2407 8/1/2022 Gr. Beta 11.1 +/- 2.6 10.5 +/- 2.4 10.8 +/- 1.8 Pass W -2406,2407 8/1/2022 Ra-226 1.83 +/- 0.28 2.31 +/- 0.35 2.07 +/- 0.22 Pass W -2406,2407 8/1/2022 Ra-228 2.87 +/- 0.95 2.43 +/- 0.93 2.65 +/- 0.66 Pass DW -40213,40214 8/3/2022 Gr. Alpha 0.60 +/- 0.60 -0.30 +/- 0.70 0.15 +/- 0.46 Pass DW -40213,40214 8/3/2022 Gr. Beta 0.72 +/- 0.59 0.85 +/- 0.54 0.79 +/- 0.40 Pass DW -40225,40226 8/10/2022 Ra-226 0.53 +/- 0.13 0.41 +/- 0.10 0.47 +/- 0.08 Pass
A-12 TABLE A-5. Intralaborator y "Duplicate" Samples
Concentrationa Averaged Lab Codeb Date Analysis AcceptanceFirst ResultSecond ResultResult
DW -40225,40226 8/10/2022 Ra-228 1.20 +/- 0.71 1.00 +/- 0.71 1.10 +/- 0.50 Pass S-2553,2554 8/18/2022 K-40 1.74 +/- 0.27 1.33 +/- 0.22 1.54 +/- 0.17 Pass W W -2774,2775 8/19/2022 H-3 138 +/- 86 171 +/- 88 155 +/- 62 Pass S-2797,2798 8/22/2022 K-40 19.0 +/- 0.2 18.7 +/- 0.2 18.9 +/- 0.1 Pass DW -40241,40242 8/23/2022 Ra-226 3.10 +/- 0.19 3.54 +/- 0.19 3.32 +/- 0.13 Pass DW -40241,40242 8/23/2022 Ra-228 6.05 +/- 0.98 6.61 +/- 1.02 6.33 +/- 0.71 Pass W -2681,2682 8/24/2022 H-3 1054 +/- 126 962 +/- 122 1008 +/- 88 Pass DW -40259,40260 8/30/2022 Ra-228 0.49 +/- 0.11 0.11 +/- 0.10 0.30 +/- 0.07 Pass DW -40259,40260 8/30/2022 Ra-226 0.49 +/- 0.11 0.11 +/- 0.09 0.30 +/- 0.07 Pass DW -40259,40260 8/30/2022 Ra-228 0.00 +/- 0.57 0.47 +/- 61.00 0.24 +/- 30.50 Pass AP-830227A,B 8/30/2022 Gr. Beta 0.027 +/- 0.004 0.026 +/- 0.004 0.027 +/- 0.003 Pass AP-808227A,B 8/30/2022 Gr. Beta 0.016 +/- 0.004 0.018 +/- 0.004 0.017 +/- 0.003 Pass VE-2702,2703 8/30/2022 K-40 2.58 +/- 0.12 2.62 +/- 0.27 2.60 +/- 0.15 Pass VE-2702,2703 8/30/2022 Be-7 0.21 +/- 0.05 0.30 +/- 0.13 0.26 +/- 0.07 Pass VE-2702,2703 8/30/2022 Sr-90 0.002 +/- 0.001 0.002 +/- 0.001 0.002 +/- 0.001 Pass
SG-3978,3979 9/7/2022 Gr. Alpha 470 +/- 29 552 +/- 32 511 +/- 22 Pass SG-3978,3979 9/7/2022 Pb-214 31.3 +/- 0.8 30.9 +/- 1.6 31.1 +/- 0.9 Pass SG-3978,3979 9/7/2022 Ac-228 41.6 +/- 1.5 43.2 +/- 2.8 42.4 +/- 1.6 Pass SG-2844 9/9/2022 Gr. Alpha 25.7 +/- 4.0 18.7 +/- 3.5 22.2 +/- 2.7 Pass SG-2844 9/9/2022 Gr. Beta 21.3 +/- 2.0 22.2 +/- 2.0 21.8 +/- 1.4 Pass SG-2844 9/9/2022 Pb-214 4.35 +/- 0.12 4.43 +/- 0.10 4.39 +/- 0.08 Pass SG-2844 9/9/2022 Ac-228 5.37 +/- 0.22 5.39 +/- 0.17 5.38 +/- 0.14 Pass DW -40279,40280 9/9/2022 Ra-226 3.92 +/- 0.23 4.18 +/- 0.25 4.05 +/- 0.17 Pass DW -40279,40280 9/9/2022 Ra-228 7.05 +/- 1.09 6.58 +/- 1.06 6.82 +/- 0.76 Pass SG-2841,2842 9/9/2022 Pb-214 0.90 +/- 0.50 1.16 +/- 0.12 1.03 +/- 0.26 Pass SG-2841,2842 9/9/2022 Ac-228 0.91 +/- 0.10 0.88 +/- 0.17 0.90 +/- 0.10 Pass DW -40295,40296 9/13/2022 Gr. Alpha 0.79 +/- 0.97 0.64 +/- 0.97 0.72 +/- 0.69 Pass DW -40295,40296 9/14/2022 Ra-226 2.75 +/- 0.32 2.89 +/- 0.24 2.82 +/- 0.20 Pass DW -40295,40296 9/14/2022 Ra-228 2.88 +/- 0.78 2.95 +/- 0.76 2.92 +/- 0.54 Pass SG-2862,2863 9/14/2022 Pb-214 11.8 +/- 0.2 11.2 +/- 0.2 11.5 +/- 0.1 Pass SG-2862,2863 9/14/2022 Ac-228 6.95 +/- 0.24 7.18 +/- 0.19 7.07 +/- 0.15 Pass SG-3119,3120 9/24/2022 Pb-214 3.10 +/- 0.21 3.10 +/- 0.22 3.10 +/- 0.15 Pass SG-3119,3120 9/24/2022 Ac-228 2.16 +/- 0.38 2.30 +/- 0.33 2.23 +/- 0.25 Pass SG-3075,3076 9/28/2022 Gr. Alpha 174 +/- 10 158 +/- 10 166 +/- 7 Pass SG-3075,3076 9/28/2022 Pb-214 23.6 +/- 0.9 24.4 +/- 0.4 24.0 +/- 0.5 Pass SG-3075,3076 9/28/2022 Ac-228 38.2 +/- 1.9 35.8 +/- 0.8 37.0 +/- 1.0 Pass DW -40318,40319 9/29/2022 Gr. Alpha 1.02 +/- 0.94 1.79 +/- 1.68 1.41 +/- 0.96 Pass
AP-100321A/B 10/3/2022 Gr. Beta 0.015 +/- 0.003 0.011 +/- 0.003 0.013 +/- 0.002 Pass SO-3140,3141 10/3/2022 Be-7 0.353 +/- 0.180 0.304 +/- 0.163 0.328 +/- 0.121 Pass SO-3140,3141 10/3/2022 K-40 11.2 +/- 0.6 11.0 +/- 0.6 11.1 +/- 0.4 Pass SO-3140,3141 10/3/2022 Cs-137 0.055 +/- 0.016 0.069 +/- 0.020 0.062 +/- 0.013 Pass SO-3140,3141 10/3/2022 Tl-208 0.132 +/- 0.022 0.114 +/- 0.024 0.123 +/- 0.016 Pass
A-13 TABLE A-5. Intralaborator y "Duplicate" Samples
Concentration a Averaged Lab Codeb Date Analysis AcceptanceFirst ResultSecond ResultResult
SO-3140,3141 10/3/2022 Bi-214 0.315 +/- 0.041 0.390 +/- 0.041 0.353 +/- 0.029Pass SO-3140,3141 10/3/2022 Pb-212 0.344 +/- 0.029 0.357 +/- 0.029 0.351 +/- 0.020Pass SO-3140,3141 10/3/2022 Pb-214 0.362 +/- 0.043 0.446 +/- 0.047 0.404 +/- 0.032Pass SO-3140,3141 10/3/2022 Ra-226 0.602 +/- 0.250 0.768 +/- 0.248 0.685 +/- 0.176Pass SO-3140,3141 10/3/2022 Ac-228 0.442 +/- 0.101 0.405 +/- 0.083 0.423 +/- 0.066Pass SO-3140,3141 10/3/2022 Gr. Alpha 4.07 +/- 1.77 4.43 +/- 2.17 4.25 +/- 1.40Pass SO-3140,3141 10/3/2022 Gr. Beta 15.6 +/- 1.6 17.0 +/- 1.5 16.3 +/- 1.1Pass AP-101021A/B 10/10/2022 Gr. Beta 0.037 +/- 0.005 0.040 +/- 0.005 0.039 +/- 0.004Pass S-3501,3502 10/18/2022 K-40 16.3 +/- 1.2 16.3 +/- 1.3 16.3 +/- 0.9Pass AP-101821A/B 10/18/2022 Gr. Beta 0.026 +/- 0.003 0.027 +/- 0.003 0.026 +/- 0.002Pass DW -40328,40329 10/25/2022 Ra-226 2.13 +/- 0.18 2.17 +/- 0.28 2.15 +/- 0.17Pass AP-102621A/B 10/26/2022 Gr. Beta 0.051 +/- 0.005 0.047 +/- 0.005 0.049 +/- 0.003Pass
SG-3557,3558 11/1/2022 Gr. Alpha 24.5 +/- 4.0 25.0 +/- 4.0 24.8 +/- 2.8Pass SG-3557,3558 11/1/2022 Gr. Beta 26.7 +/- 2.2 29.3 +/- 2.3 28.0 +/- 1.6Pass SG-3557,3558 11/1/2022 Pb-214 9.23 +/- 0.15 9.23 +/- 0.32 9.23 +/- 0.18Pass SG-3557,3558 11/1/2022 Ac-228 7.35 +/- 0.31 8.26 +/- 0.63 7.81 +/- 0.35Pass AP-110221A/B 11/2/2022 Gr. Beta 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.002Pass DW -40341,40342 11/7/2022 Ra-226 1.18 +/- 0.15 0.89 +/- 0.14 1.04 +/- 0.10Pass DW -40341,40342 11/7/2022 Ra-228 1.98 +/- 0.95 3.32 +/- 1.12 2.65 +/- 0.73Pass AP-110921A/B 11/9/2022 Gr. Beta 0.025 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.002Pass AP-111621A/B 11/16/2022 Gr. Beta 0.013 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002Pass AP-112321A/B 11/23/2022 Gr. Beta 0.034 +/- 0.004 0.031 +/- 0.004 0.032 +/- 0.003Pass AP-113021A/B 11/30/2022 Gr. Beta 0.056 +/- 0.005 0.058 +/- 0.005 0.057 +/- 0.003Pass
SG-4016,4017 12/5/2022 Gr. Alpha 24.5 +/- 4.0 25.0 +/- 4.0 24.7 +/- 2.9Pass SG-4016,4017 12/5/2022 Gr. Beta 26.7 +/- 2.2 29.3 +/- 2.3 28.0 +/- 1.6Pass SG-4016,4017 12/5/2022 Pb-214 8.64 +/- 0.30 9.28 +/- 0.30 8.96 +/- 0.21Pass SG-4016,4017 12/5/2022 Ac-228 10.8 +/- 0.8 10.0 +/- 0.8 10.4 +/- 0.6Pass AP-120721A/B 12/7/2022 Gr. Beta 0.034 +/- 0.003 0.030 +/- 0.003 0.032 +/- 0.002Pass DW -40375,40376 12/14/2022 Ra-228 5.05 +/- 0.96 7.15 +/- 1.09 6.10 +/- 0.73Pass DW -40375,40376 12/14/2022 Ra-226 3.33 +/- 0.27 4.28 +/- 0.29 3.81 +/- 0.20Pass AP-121621A/B 12/16/2022 Gr. Beta 0.039 +/- 0.004 0.033 +/- 0.004 0.036 +/- 0.003Pass AP-122721A/B 12/27/2022 Gr. Beta 0.018 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.001Pass AP-122821A/B 12/28/2022 Gr. Beta 0.042 +/- 0.003 0.039 +/- 0.003 0.041 +/- 0.002Pass
Note: Duplicate analyses are performed on every twentieth sample received. Results are not listed for those analyses with activities that measure below the LLD.
a Results are reported in units of pCi/L, except for air filt ers (pCi/Filter or pCi/m3 ), food products, vegetation,
soil and sediment (pCi/g).
b AP (Air Particulate), AV (Aquatic Vegetation), BS (Bottom Sediment), CF (Cattle F eed), CH (Charcoal Canister),
DW (Drinking W ater), E (Egg), F (Fis h), G (Grass), LW (Lake W ater), MI (Milk ), P (Precipitation), PM (Powdered Milk),
S (Solid), SG (Sludge), SO (Soil), SS (Shoreline Sediment), SW (Surfac e W ater), SW T (Surface W ater Treated),
SW U (Surface W ater Untreated), U (Uri ne), VE (Vegetation), W (W ater), W W (W ell W ater).
A-14 TABLE A-6. Department of Energy's Mixed Analyte Performance Ev aluation Program (MAPEP).
Concentrationa Reference KnownControl Lab Code b Date Analysis Activity AcceptanceLaboratory resultLimits c
MAAP-506 2/1/2022 Gross Alpha 1.10 +/- 0.14 1.20 0.36 - 2.04 Pass MAAP-506 2/1/2022 Gross Beta 0.83 +/- 0.06 0.681 0.341 - 1.022 Pass
MADW -408 2/1/2022 Gross Alpha 0.34 +/- 0.04 0.574 0.172 +/- 0.976 Pass MADW -408 2/1/2022 Gross Beta 6.61 +/- 0.09 7.25 3.63 - 10.88 Pass
MASO-504 2/1/2022 Cs-134 738 +/- 8 890 623 - 1157 Pass MASO-504 2/1/2022 Cs-137 399 +/- 9 365 256 - 475 Pass MASO-504 2/1/2022 Co-57 1479 +/- 375 1400 980 - 1820 Pass MASO-504 2/1/2022 Co-60 433 +/- 6 443 310 - 576 Pass MASO-504 2/1/2022 Mn-54 1258 +/- 606 1140 798 - 1482 Pass MASO-504 2/1/2022 Zn-65 -2.11 +/- 4.44 0 NA c Pass MASO-504 2/1/2022 K-40 641 +/- 40 596 417 - 775 Pass
MADW -500 2/1/2022 Cs-134 -0.06 +/- 0.11 0 NA c Pass MADW -500 2/1/2022 Cs-137 8.09 +/- 0. 33 7.64 5.35 - 9.93 Pass MADW -500 2/1/2022 Co-57 37.04 +/- 0.55 36.0 25.20 - 46.80 Pass MADW -500 2/1/2022 Co-60 8.91 +/- 0.27 9.3 6.5 - 12.1 Pass MADW -500 2/1/2022 Mn-54 20.4 +/- 0.6 18.9 13.2 - 24.6 Pass MADW -500 2/1/2022 Zn-65 28.65 +/- 0.94 26.2 18.3 - 34.1 Pass MADW -500 2/1/2022 K-40 4.80 +/- 2.57 0 NA c Pass
MADW -500 2/1/2022 H-3 309 +/- 10 300 210 - 390 Pass MADW -500 2/1/2022 Ra-226 0.83 +/- 0.10 0.8 0.6 - 1.0 Pass MADW -500 2/1/2022 U-234 0.13 +/- 0.01 1.5 1.1 - 2.0Fail d MADW -500 2/1/2022 U-238 0.12 +/- 0.01 1.54 1.08 - 2.00 Fail d
MAAP-502 2/1/2022 Cs-134 0.83 +/- 0. 05 0.93 0.65 - 1.21 Pass MAAP-502 2/1/2022 Cs-137 0.87 +/- 0.07 0.726 0.51 - 0.94 Pass MAAP-502 2/1/2022 Co-57 0.87 +/- 0.05 0 NA c Fail e MAAP-502 2/1/2022 Co-60 0.83 +/- 0. 07 0.72 0.50 - 0.94 Pass MAAP-502 2/1/2022 Mn-54 0.02 +/- 0.02 0 NA c Pass MAAP-502 2/1/2022 Sr-90 0.72 +/- 0.10 0.54 0.38 - 0.70 Fail f
MAVE-507 2/1/2022 Cs-134 7.53 +/- 0. 17 7.61 5.33 - 9.89 Pass MAVE-507 2/1/2022 Cs-137 1.60 +/- 0. 12 1.52 1.06 - 1.98 Pass MAVE-507 2/1/2022 Co-57 6.21 +/- 0. 17 5.09 3.56 - 6.62 Pass MAVE-507 2/1/2022 Co-60 0.01 +/- 0.03 0 NA c Pass MAVE-507 2/1/2022 Mn-54 2.940 +/- 0.140 3 1.81 - 3.37 Pass MAVE-507 2/1/2022 Zn-65 1.69 +/- 0.17 1.47 1.03 - 1.91 Pass
MADW -2613 8/1/2022 Gross Alpha 1. 39 +/- 0.10 0.90 0.27 - 1.53 Pass MADW -2613 8/1/2022 Gross Beta 1. 69 +/- 0.04 1.31 0.66 - 1.97 Pass
A-15 TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration a Reference KnownControl Lab Code b Date Analysis Activity AcceptanceLaboratory resultLimits c
MASO-2737 8/1/2022 Cs-134 523 +/- 5 627 439 - 815 Pass MASO-2737 8/1/2022 Cs-137 1.18 +/- 2.21 0NA c Pass MASO-2737 8/1/2022 Co-57 715 +/- 6 786 550 - 1022 Pass MASO-2737 8/1/2022 Co-60 -0.04 +/- 1.07 0NA c Pass MASO-2737 8/1/2022 Mn-54 903 +/- 11 841 589 - 1093 Pass MASO-2737 8/1/2022 Zn-65 1227 +/- 19 1140 798 - 1482 Pass MASO-2737 8/1/2022 K-40 595 +/- 37 537 376 - 698 Pass
MADW -2733 8/1/2022 Cs-134 13.6 +/- 0.3 17.1 12.0 - 22.2 Pass MADW -2733 8/1/2022 Cs-137 16.0 +/- 0.4 16.8 11.8 - 21.8 Pass MADW -2733 8/1/2022 Co-57 27.5 +/- 0.4 30.0 21.0 - 39.0 Pass MADW -2733 8/1/2022 Co-60 14.4 +/- 0.3 17.0 11.9 - 22.1 Pass MADW -2733 8/1/2022 Mn-54 -0.03 +/- 0.10 0NA c Pass MADW -2733 8/1/2022 Zn-65 11.5 +/- 0.6 11.3 7.9 - 14.7 Pass MADW -2733 8/1/2022 K-40 3.88 +/- 1.51 0NA c Pass MADW -2733 8/1/2022 Sr-90 6.79 +/- 0.32 7.73 5.41 - 10.05 Pass
MAAP-2735 8/1/2022 Cs-134 -0.001 +/- 0.029 0 NA c Pass MAAP-2735 8/1/2022 Cs-137 1.76 +/- 0. 11 1.53 1.07 - 1.99 Pass MAAP-2735 8/1/2022 Co-57 3.50 +/- 0. 07 3.32 2.32 - 4.32 Pass MAAP-2735 8/1/2022 Co-60 2.11 +/- 0. 08 1.99 1.39 - 2.59 Pass MAAP-2735 8/1/2022 Mn-54 2.18 +/- 0.13 1.88 1.32 - 2.44 Pass MAAP-2735 8/1/2022 Zn-65 1.83 +/- 0.22 1.58 1.11 - 2.05 Pass
MAVE-2740 8/1/2022 Cs-134 0.01 +/- 0.06 0NA c Pass MAVE-2740 8/1/2022 Cs-137 1.15 +/- 0.12 1.083 0.758 - 1.408 Pass MAVE-2740 8/1/2022 Co-57 -0.003 +/- 0.035 0NA c Pass MAVE-2740 8/1/2022 Co-60 4.71 +/- 0. 14 4.62 3.23 - 6.01 Pass MAVE-2740 8/1/2022 Mn-54 2.67 +/- 0.19 2.43 1.70 - 3.16 Pass MAVE-2740 8/1/2022 Zn-65 7.73 +/- 0.39 7.49 5.24 - 9.74 Pass
a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
b Laboratory codes as follows: MAW (water), MADW (water), MAAP (air filter), MASO (soil) and MAVE (vegetation).
c MAPEP results are presented as the known values and expect ed laboratory precision (1 sigma, 1 determination) and
control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.
d Results for a different dataset were mistakenly input into the MAPEP system. If the correct dataset had been entered,
the results, (U-234: 1.62 +/- 0.04, U-238: 1.69 +/- 0.04), would have been within the aceptance range.
e MAPEP likely added Eu-152 as an interference to Co-57. Reanalyzing the spectra in duplicate with libraries to account
for both Co-57 and Eu-152 yields Co-57 results of 0.03 +/- 0.04 & 18 +/- 0.18 Bq/sample. W hich satisfies MAPEP criteria for passing a "false positive" test.
f The analysis of this sample was repeated and the result, (Sr-90: 0.52 +/- 0.09), was within the acceptance range.
A-16 TABLE A-7. Interlaboratory Compar ison Crosscheck Program, Environment al Resource Associates (ERA) a.
MRAD-30 Study Concentration a Lab Code b Date Analysis ERA Laboratory Control Result Value c AcceptanceLimits d
ERAP-640 3/21/2022 Cs-134 458 549 356 - 673 Pass ERAP-640 3/21/2022 Cs-137 1430 1,320 1,080 - 1730 Pass ERAP-640 3/21/2022 Co-60 913 885 752 - 1120 Pass ERAP-640 3/21/2022 Mn-54 < 4.1 < 35.0 0.00 - 35.0 Pass ERAP-640 3/21/2022 Zn-65 771 671 550 - 1030 Pass
ERAP-639 3/21/2022 Gross Alpha 93.5 94.2 49.2 - 155 Pass ERAP-639 3/21/2022 Gross Beta 60.7 66.8 40.5 - 101.0 Pass
a Results obtained by Envi ronmental, Inc., Midwest Laboratory (EIML) as a participant in the cr osscheck program for proficiency testing administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laborato ry Quality Assessment Program (EML).
b Laboratory code ERAP (air filter). Results are reported in units of (pCi/Filter).
c The ERA Assigned values for the air filter standards are equal to 100% of the parameter present in the standard as determined by the gravimetric and/or volumetric meas urements made during standard preparation as applicable.
d The acceptance limits are established per the guid elines contained in the D epartment of Energy (DOE) report EML-564, Analysis of En vironmental Measurements Laboratory (EM L) Quality Assessment Program (QAP)
Data Determination of Operational Criteria and Control Limits fo r Performance Evaluati on Purposes or ERA's SOP for the generation of Performance Acceptance Limits.
A-17
~ L. ATI Environmental, Inc.,.~ r\\l Midwest Laboratory
700 Landwehr Road
- Northbrook, IL 60062-2310 phone (847) 564-0700
- fax (847) 564-4517
Appendix B
Data Reporting Conventions
APPENDIX B. DATA REPORTING CONVENTIONS
Data Reporting Conventions
1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements
Each single measurement is reported as follows: x +/- s where: x = value of the measurement; s = 2V counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66 V uncertainty for a background sample.
3.0. Duplicate analyses
If duplicate analyses are reporte d, the convention is as follows. :
3.1 Individual results: For two analysis results; x 1 +/- s1 and x2 +/- s2 Reported result: x +/- s; where x = (1/2) (x1 + x2) and s = (1/2) s 22 1 s2
3.2. Individual results: < L 1, < L2 Reported result: < L, where L = lower of L 1 and L2
3.3. Individual results: x +/- s, < L Reported result: x +/- s if x L; < L otherwise.
4.0. Computation of Aver ages and Standard Deviations
4.1 Averages and standard deviations listed in the tables are computed from all of the individual meas urements over the period averaged; for example, an annual stan dard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x 1, x2... xn are defined as follows:
x = 1 x s = - (x-x)2 n n-1
4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are le ss than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an exampl e, 11.443 is rounded off to 11.44.
4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.
B-1
~ L. ATI Environmental, Inc.,.~ r\\l Midwest Laboratory
700 Landwehr Road
- Northbrook, IL 60062-2310 phone (847) 564-0700
- fax (847) 564-4517
Appendix C
Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas APPENDIX C
Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa.
Air (pCi/m3) Water (pCi/L)
Gross alpha 1 x 10-3 Strontium-89 8,000
Gross beta 1 Strontium-90 500
Iodine-131b 2.8 x 10-1 Cesium-137 1,000
Barium-140 8,000
Iodine-131 1,000 Potassium-40 c 4,000
Gross alpha 2
Gross beta 10
Tritium 1 x 106
a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
b Value adjusted by a factor of 700 to reduce the dose resulting from the air -grass-cow-milk-child pathway.
c A natural radionuclide.
C-1 APPENDIX D
Sample Collection and Analysis Program
D-1 TLO LOCATIONS ONE MILE RADIUS
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0 PRAIRIE IS LAND TLD POINTS
D-2
TLO LOCATIONS
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6 I
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CONTROL POINTS PRESCOTT, WISCONSIN
MONITORING LEGEND:
0 PRAIRIE ISLAND TLD POINTS
D-3
TLD LOCATIONS FIVE MILE RAOlUS
MONITORING LEGEND:
0 PRAIRIE ISLAND TLO POINTS
D-4
E NV IR ONM ENTAL SAMPLING POINTS ONE MILE RADIUS
PLANT AREA EN LARGED PLAN [1.00 MILE RADIUS)
(NO SCALE]
MONITOR ING LEGEND
AlR SAMPLING POINT ID NUMBER S FISH SAMPLING POINT ID NUMBERS P-1, P-2, P*3, P*-4, P -6, P-7 P*\\3, P-19
WATER SAMPLING PO I NT ID NU MBERS JNVERTEBRA TES POINT IQ NUMB ERS P*5, P-S. P*8, P*'l, P*ll. P-24, P-43 P*6, P*40
VEG ETATION I VEOE1ABLE S ID NUMBERS SEDIMENT SAMPLING POINT !O NUMBERS P-28. P-38. P-45 P*S, P*l2, P-20
D-5
ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS
MONITORING LEGEND
AIR SAMPU NG P0JNT 10 NUMBERS FISH SAMPLING POINT ID NUMBERS P-l. P-2. P-3, P-4. P - 6, P-7 P*l3. P*l'l
W,TER 5A'l'1PUNG POINT I[} NUMBERS fNV ER TEBRMES POINT JD NUMBERS 0 P-5, P-S. P-8, P-'l. P-11. P-24, P-4 3 P-6. P-40
VE GE TATION I vEGE rABLES JO NUM BERS SEDIMENT SAMPLING POlNl 10 NU ~BERS P-2 8, P*38, P-45 P-6, P-12, P-20
D-6
ENVIRONMENTAL SAMPLING POINTS
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0 P-43, Peterson Farm, W10322 SI Rd 29, River Falls, WI 0 P-38, Caln Residence, N7395 950th SI, River Falls, WI
CONTROL POINTS PRESCOTT, WISCONSIN
MONITORING LEGEND
AIR SAMPLING POINT 10 NUMBERS P-1, P-2, P -3, P-4, P-6, P-7
WATER SAMPLING POINT 10 NUM BERS P-6, P-6, P-8, P-9, P-11, P-43
VEGETAT ION I V EGETABLES 10 NUMBERS P-28, P-38, P-46
D-7
APPENDIX E
Special W ell and
Surface W ater Samples
E-1
1.0 INTRODUCTION
This appendix to the Radiological Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the special well and surface water samples taken at the Prairie Island Nuclear Generating Plant, Red W ing, Minnesota, during the period January - December, 2022. This supplemental special sampling program was established in December of 1989 when higher than expected levels of tritium were detected in a nearby residence well sample.
Tabulations of the special sampling program individual analyses made during the year are included in this appendix. A summary table of tritium analyses is also included in this appendix.
2.0
SUMMARY
This special sampling program was established following the detection of tritium in a residence well water sample south of the PINGP during 1989. This program is described and the results for 2022 are summarized and discussed.
Program findings for 2022 detected low levels of tritium in nearby residence wells, ground water, surface samples, and storage tanks at or near the expected natural background levels with the exception of ground water sample well MW -8, parking lot runoff, MW 7/8 area snow, and the septic system. The 2022 sample results (except for MW -8, parking lot runoff, MW 7/8 area snow, and the septic system) ranged from <19 pCi/L to 180 pCi/L. Sample well MW -8 ranged from 204 pCi/L to 716 pCi/L. Parking lot runoff ranged from 40 to 245 pCi/L. MW 7/8 area snow was 1116 pCi/L. The septic system ranged from 31 to 1892 pCi/L. All tritium results are far below the Environmental Protection Agencys drinking water standard of 20,000 pCi/L and present no harm to any members of the public.
None of the water samples monitored for gamma-emitting isotopes showed any activity greater than the LLD.
E-2 3.0 Special Tritium Sampling Program
3.1 Program Design and Data Interpretation
The purpose of this sampling program is to assess the impact of any tritium leaching into the environment (ground water system) from the PINGP. For this purpose, special water samples are collected and analyzed for tritium content.
3.2 Program Description
The sampling and analysis schedule for the special water sampling program is summarized in Table E-4.1 and briefly reviewed below. Table E-4.2 defines the additional sample locations and codes for the special water sampling program.
Special well, tank, and surface water samples were collected quarterly (spring, summer, fall) at seven locations, quarterly at one location, monthly at six locations, semi-annually at five locations, and annually at thirty-nine locations. The Peterson (P-43) and Hanson (SW -1) farm wells are used as control locations for these special samples.
To detect low levels of tritium at or below natural background levels, analyses of the samples have been contracted to a laboratory (University of W aterloo Laboratories) capable of detecting tritium concentrations down to 19 pCi/L. W aterloo Laboratories report tritium analyses results in Tritium Units (1 TU = 3.2 pCi/L). The tritium results in this report are indicated in pCi/L.
3.3 Program Execution
The special water sampling was executed as described in the preceding section.
3.4 Program Modifications
Changes to the program in 2022 include:
x Samples taken from monitoring wells P-10 and MW-8 were sent to Environmental Incorporated for hard-to-detect nuclide analysis in accordance with American Nuclear Insurers recommendation x No samples were taken from the D5/D6 Fuel Oil Storage Tank vaults because these areas were dry in 2022 x Sampling point S-10 (Barrelyard SW Storm W ater Drain) was added to the sampling program in October, 2022, as an enhancement recommended by an Electric Power Research Institute audit
E-3 3.5 Results and Discussion
Results show tritium in well water and ground water samples at or near expected natural background levels except the MW -8 ground water sample well. Table E-4.4 provides the complete data table of results for each period and sampling location.
The tritium level annual averages have shown a downward trend since the special sampling began in 1989.
Except for sample well MW -8, parking lot runoff, MW 7/8 area snow, and the septic system, the 2022 sample results are within the range of expected background tritium levels in shallow ground water and surface water due to tritium concentrations measured in precipitation. Sampling points in North America have shown tritium concentrations in precipitation ranging from 5 pCi/L to 157 pCi/L (Environmental Isotope Data No. 10; W orld Survey of Isotope Concentration in Precipitation (1988-1991)).
The higher-level results at the Suter residence and Birch Lake in 1989 were possibly due to seepage from the PINGP discharge canal water into the ground water. This is thought to occur due to the elevation difference between the Vermillion River and the discharge canal. The Suter residence is located between the discharge canal and Birch Lake, which connects to the Vermillion River. The PINGP discharge canal piping was lengthened during 1991, so that liquid discharges from the plant are released near the end of the discharge canal, diffused and discharged to the Mississippi River. In 1992, the underground liquid discharge pipe from the plant to the discharge canal piping was replaced with a double walled leak detectable piping system. This years sample results continue to indicate that these modifications have eliminated the suspected radioactive effluent flow into the local ground water.
The elevated tritium levels in sample well MW -8 in 2022 may be due to prior leakage from the PINGP liquid radwaste discharge pipe, discharge of turbine building sump water into the landlocked area, or discharge of heating steam condensate from the main warehouse in 1978/1979. The liquid radwaste discharge pipe was replaced in 1992 and the discharge to the landlocked area has been terminated, the last discharge took place on 11/14/09. The main warehouse heating system was repaired in 1979. The heating steam system has not been used in the outer plant buildings since the 2011 - 2012 heating season.
The elevated tritium levels in the parking lot runoff and MW 7/8 area snow are most likely due to tritium recaptured from effluent releases by precipitation. The levels found in the septic system have returned to background levels.
None of the water samples monitored for gamma-emitting isotopes showed any activity greater than the LLD.
E-4 Table E-4.1. Sample collection and analysis program for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2022.
Medium No. Location codes Collection type Analysis and type a and frequency b type c
P-8 post-treat, P-8 pre-treat, REMP P-6, REMP P-11, PIIC-22, Well water PIIC-26, PIIC-28, PIIC-29, P-7, P-9, Annual 25P-11, PZ-1, PZ-2, PZ-4, PZ-5, PZ-7, G/A H-3 MW -6, P-26, P-30, SW -3, SW -4, SW -5, SW -7, SW -8, SW -9
W ell water quarterly 1 P-24D G/Q H-3
W ell water quarterly 7 P-2, P-3, P-5, P-6,PZ-8, MW -4, MW -5 G/Q H-3
W ell water monthly 5 P-43(C), SW -1(C),MW -7, MW -8, P-10 G/M H-3
Surface water S-1, S-2, S-3, S-4, S-5, 9 S-6, S-7, S-10, P-31 G/Ad H-3
Storage Tank 5 11 CST, 21 CST, 22 CST, U1/2 Demin Hdr G/S H-3
Storage Tank 1 Septic System G/M H-3
Snow 5 S-6, S-7, S-8, S-9, P-43(C) G/A H-3
a Location codes are defined in table D-4.2. Control Stations are indicated by (C). All other stations are indicators.
b Collection type is codes as follows: G/ = grab. Collection frequency is coded as follows: M = monthly; Q = quarterly; Q = quarterly (spring, summer, and fall) ; S= semiannually; A = annually.
c Analysis type is coded as follows: H-3 = tritium.
d Location S-6, S-7, and S-10 are sampled semi-annu ally, P-31 is sampled three times a year
E-5 Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2022.
Code Collection siteType ofDistance and sample a direction from reactor
P-8 PI Community well post treat DW 1.0 mi. @ 321°/W NW P-8 PI Community well pre treat DW 1.0 mi. @ 321°/W NW REMP P-6 Lock & Dam #3 well DW 1.6 mi. @ 129°/SE REMP P-11 Red W ing Service Center DW 3.3 mi @ 158°/SSE PIIC-22 1773 Buffalo Slough Rd DW 1 mi. @ 315°/NW PIIC-26 1771 Buffalo Slough Rd DW 1 mi. @ 315°/NW PIIC-29 Buffalo Project DW 4.3 mi @ 302°/W NW P-24D Suter residence DW 0.6 mi. @ 158°/SSE P-43 Peterson Farm (Control) DW 13.9 mi. @ 355°/N SW -1 Hanson Farm (Control) DW 2.2 mi. @ 315°/NW P-2 Sample well WW See map P-3 Sample well WW See map P-5 Sample well WW See map P-6 Sample well WW See map P-7 Sample well WW See map P-10 Sample well WW See map P-11 Sample well WW See map PZ-1 Sample well WW See map PZ-2 Sample well WW See map PZ-4 Sample well WW See map PZ-5 Sample well WW See map PZ-7 Sample well WW See map PZ-8 Sample well WW See map MW -4 Sample well WW See map MW -5 Sample well WW See map MW -6 Sample well WW See map MW -7 Sample well WW See map MW -8 Sample well WW See map P-26 PITC well DW 0.4 mi. @ 258°/W SW P-30 Environ lab well DW 0.2 mi. @ 32°/NNE
E-6 Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2022 (continued).
Code Collection siteType ofDistance and sample a direction from reactor
SW -3 Cooling Tower pump WW See map SW -4 New Admin Bldg DW 0.05 mi. @ 315 /NW SW -5 Plant Screenhouse well WW 0.05 mi. @ 0/N SW -6 SGR Building DW 0.2 mi @ 310 /NW SW -7 Distribution Center DW 0.35 mi @ 271 /W SW -8 Site Admin Building well WW 0.2 mi @ 310 /NW SW -9 FLEX Building WW 0.2 mi @ 238°/W SW P-9 Plant well # 2 DW 0.3 mi. @ 306°/NW S-1 Upstream Miss. River SW See map S-2 Recirc/Intake canal SW See map S-3 Cooling water canal SW See map S-4 Discharge Canal (end) SW See map S-5 Mid Discharge Canal SW See map S-6 Roof Stormwater Runoff (also snow) SW 0.05 mi. @ 0/N S-7 Parking Lot Stormwater (also snow) SW 0.3 mi @ 306 /NW S-8 P-10 area snow SW See map S-9 MW -7/8 area snow SW See map S-10 Barrelyard SW Storm W ater Drain SW Outside Barrelyard P-31 Birch Lake Seepage SW 0.69 mi. @ 172°/S 11 CST Storage Tank ST Turbine Building 21 CST Storage Tank ST Turbine Building 22 CST Storage Tank ST Turbine Building Unit 1/2 demin hdr Storage Tank ST Turbine Building Septic System Storage Tank ST Outside #1 W arehouse D5 Vault Concrete Vault ST Outside Turbine Bldg D6 Vault Concrete Vault ST Outside Turbine Bldg
a Sample codes: DW = Drinking W ater: W W = W ell W a ter; SW = Surface W ater: ST = Storage Tank.
E-7 Table E-4.3 Radiation Environmental Monitoring Program Summary: Special well, storage tank, and surface water samples.
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January - December, 2022 (County, State)
Indicator Location with Highest Control Locations Annual Mean Locations
Sample Type and Mean (F) c Number Type Number of LLD b Range c Location d Mean (F) cRange c Mean (F) cRange cNon-(Units) Analyses a Routine Results e
Offsite Well H-3 13 19 26 (4/13) PIIC-22 33 (1/1)(See Control Water (22-33) (33) Below) 0 (pCi/L)
Onsite H-3 74 19 162 (53/74) MW -8 496 (12/12)(See Control Well Water (19-716) (204-716) Below) 10 (pCi/L)
Onsite H-3 17 19 183 (13/17) S-9 1116 (1/1)(See Control Surface W ater (24-1116) (1116) Below) 2 (pCi/L)
Onsite H-3 22 19 236 (15/22) 283 (12/12) (See Control Storage Tank (24-1892) Septic System (31-1892) Below) 2 (pCi/L)
Control (offsite H-3 24 19 none P-43 32 (5/12)31 (6/24) well water) (21-46) (21-46) 0
Control (offsite H-3 1 19 none P-43 35 (1/1)35 (1/1) snow) (35) (35) 0
a H-3 = tritium b LLD = Nominal lower limit of detection based on 4.66 sigma error for background sample. Value shown is lowest for the period.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified by code.
e Non-routine results are those which exceed ten times the control station mean value.
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